Mr
Alexey Likhachev
(ROSATOM)
6/26/17, 8:30 AM
Mr
Yukiya Amano
(IAEA)
6/26/17, 8:40 AM
Mr
Vyacheslav Pershukov
(ROSATOM)
6/26/17, 8:50 AM
Mr
Mikhail Chudakov
(IAEA)
6/26/17, 9:00 AM
Mr
Alexander Moiseev
6/26/17, 9:05 AM
Mr
Subhash Chander CHETAL
(India)
6/26/17, 9:15 AM
Mr
Evgeny Adamov
(Institution “ITC “PRORYV” Project)
6/26/17, 10:00 AM
This article analyzes problems and approaches to modern nuclear power development using closed nuclear fuel cycle and fast reactors. It describes specified technical requirements for nuclear power systems in large-scale nuclear power industry. Targets and scientific problems solved by Rosatom’s “PRORYV” Project which is a part of the Federal State Program “Nuclear Power Technologies of New...
Mr
Puthiyavinayagam Pillai
(Indira Gandhi Centre for Atomic Research)
6/26/17, 1:00 PM
India has been operating a Fast Breeder Test Reactor (FBTR) successfully since 1985. Currently, a 500 MWe MOX fuelled pool type Sodium cooled Fast Reactor called Prototype Fast Breeder Reactor (PFBR) is under advanced stage of commissioning. The design, R&D, safety review, construction and commissioning experience from PFBR has motivated the commercial exploitation of MOX fuelled Sodium cooled...
Mr
Seiichiro Maeda
(Japan Atomic Energy Agency)
6/26/17, 1:00 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
The next generation fast reactor is being investigated in Japan, aiming at several targets such as “safety”, “reduction of environmental burden” and “economic competitiveness”. As for the safety aspect, FAIDUS (fuel assembly with inner duct structure) concept is adopted to avoid re-criticality in core destructive accidents. The uranium-plutonium mixed oxide (MOX) fuel, in which minor actinide...
Dr
Jeong-Yong Park
(Korea Atomic Energy Research Institute)
6/26/17, 1:00 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The fabrication process of metallic fuels for sodium-cooled fast reactor (SFR) was developed using the injection casting. U-Zr-RE(Nd-Ce-Pr-La) fuel slugs were fabricated and characterized to optimize the injection casting process. The microstructure examined by SEM showed that precipitates were uniformly distributed over the fuel slug. The fuel weight loss after the injection casting was...
Dr
Dmitry Fomichev
(JSC NIKIET)
6/26/17, 1:00 PM
This paper presents an analysis of hydraulic and heat transfer phenomena in a lead coolant flow in a fuel assembly (FA) of the BREST-OD-300 reactor core central subzone based on CFD simulations (RANS) using the STAR-CCM+ code. Based on the simulation results, coolant pressure, velocity and temperature fields, and the fuel cladding temperature distribution have been obtained. The FA design...
Prof.
Koji Morita
(Kyushu University)
6/26/17, 1:00 PM
This paper describes the status of safety research activity in the field of sodium-cooled fast reactors (SFRs) in Japan, mainly on severe accident related issues. Core damage sequences are analyzed by applying probabilistic risk assessment methodology and categorized into typical accident phases, i.e., initiating phase, transitions phase, and material relocation and cooling phase. In order to...
Mr
Yuriy Nosov
(Beloyarsk NPP)
6/26/17, 1:00 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
The fast-neutron nuclear power industry development began with the BR-5/10 experimental reactors (1959) followed by BOR-60 (1969).
The power reactor evolution started with the BN350 commissioning in 1973. In 1980 the BN600 operating up to now was put into operation. In 2015 the BN800 obtained the first criticality.
BN600 fast reactor power unit No. 3 of 600 MW power has been put into...
Mr
Vladimir Usanov
(JSC «SSC RF-IPPE», State Corporation “ROSATOM”)
6/26/17, 1:20 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
Ability of nuclear power to meet the requirements of sustainable development is a critical point for public acceptance of the energy technology and its further development. The method for assessment of the nuclear energy system (NES) compatibility with the requirements of the UN concept of sustainable development was developed in the IAEA within the activities of the INPRO international...
Mr
Francois Baque
(CEA)
6/26/17, 1:20 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
In Service Inspection (ISI) of sodium cooled fast reactor prototype ASTRID implies a large R&D effort for associated tools: among others, a specific articulated carrier is being designed to allow exceptional ultrasonic controls of under-sodium core support structure (strongback) at about 200°C.
This carrier has to reach deep in the main sodium vessel and yet adapt to the many different weld...
Dr
Boris Tarasov
(NRNU MEPHI)
6/26/17, 1:20 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Choice of the fuel composition is important question to improve the competitiveness of fast reactors. It should have a high density and thermal conductivity, a high concentration of fissile nuclide, and high manufacturability. The best fuel composition of fast reactors remains a metallic nuclear fuel, based on uranium and plutonium alloys. The undeniable advantages of a metal fuel composition...
Ms
Heather Bell
(U.S. Department of Energy)
6/26/17, 1:20 PM
Plenary Session: National and International Fast Reactor Programmes
ORAL
This paper provides an overview of fast reactor research and development efforts in the United States. Fast reactors are envisioned for a wide variety of actinide management strategies ranging from actinide destruction in closed fuel cycles to enhanced uranium utilization. With successful technology development, fast reactors are also intended for electricity and heat production, as being...
Dr
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
6/26/17, 1:20 PM
One dimensional steady state model is developed for counter current shell and tube once through steam generator for PFBR with water flowing through tubes and sodium through shell. All the heat transfer processes i.e. preheating, evaporation of water and superheating of the steam happen along the length of the tube. The length of the steam generator is divided into a number of control volumes....
Mrs
Vladimir Chudanov
(Nuclear Safety Insitute RAS (IBRAE))
6/26/17, 1:40 PM
For the simulation of the thermalhydraulic processes in fast reactors with liquid metal coolant DNS CFD code CONV-3D has been developed.
This code has ideal scalability and is very effective for calculations on high performance cluster computers.
The code has been validated on the set of analytical tests and experiments in a wide range of Rayleigh and Reynolds numbers, in particular, at...
Dr
Liudmila Zabudko
(Innovative &Technology Center by "PRORYV" Project)
6/26/17, 1:40 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The nitride fuel is selected as an advanced fuel for fast reactors in Russia. Within the framework of "PRORYV" project a comprehensive program of calculation-experimental study of mixed uranium-plutonium nitride performance for BN-1200 and BREST-OD-300 reactors has been developed. The program provides for works to improve the fabrication technique, composition and structure of nitride fuel, to...
Mr
Sergey Shepelev
(JSC “Afrikantov OKBM”)
6/26/17, 1:40 PM
One of the most important stage of works for the BN-1200 power unit project, which are implemented since 2007 according to Rosenergoatom Concern JSC program and Target Federal program “Nuclear energy technologies of the new generation for 2010-2015 and for perspective to 2020”, became the development of technical designs of the RP, turbine plant and materials of the power unit project in...
Mr
Kosuke Aizawa
(Japan Atomic Energy Agency)
6/26/17, 1:40 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Inspection technique in opaque liquid metal coolant is one of important issue for sodium-cooled fast reactor. To facilitate operations and maintenance activities, various under sodium viewers (USV) has been developed in several research institutes and countries. For example, a horizontal USV, which detects obstacles on the long distance and an imaging USVs, which make images from a short...
Mr
Andrei Andrianov
(National Research Nuclear University, MEPhI)
6/26/17, 1:40 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
A performance and sustainability assessment of nuclear energy deployment scenarios with fast reactors is a multi-criteria problem which is determined by a wide spectrum of criteria characterizing resource consumption, economic performance, risks of unauthorized proliferation, safety and waste management etc. In determining the most promising scenario, it is necessary to consider the...
Mr
Stéphane BEILS
(AREVA NP)
6/26/17, 1:40 PM
ASTRID is the Advanced Sodium Technological Reactor for Industrial Demonstration which is intended to prepare the Generation IV reactor, with improvements in safety and operability. In order to meet the objectives of the 4th generation reactors and comply with the related specifications, the ASTRID project integrates innovative options.
In the earlier phase of ASTRID project, a specific...
Mr
Venkatesan Arasappan
(Indira Gandhi Centre for Atomic Research)
6/26/17, 2:00 PM
Recent advances in computer science have paved way to increased ease in design of nuclear power plants and imparting efficient operator training thereby improving the safety of nuclear plants. As nuclear power plant is considered safety critical, need to improve the skill set of the control room operators by getting the operator trained in simulator is becoming a mandatory requirement before...
Mr
Alexander Yegorov
(researcher of Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)
6/26/17, 2:00 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
The paper presents a methodological study on comparison of nuclear energy systems whose commissioning and commercial-scale operations are in the planning stage. These studies are carried out within the framework of the joint project INPRO.
Systems with numerous technical and economic uncertainties are poorly amenable to technology assessment using the INPRO methodology (for all areas, basic...
Dr
Victor BLANC
(CEA)
6/26/17, 2:00 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The French 600 MWe Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) project reached in 2015 the end of its Conceptual Design phase. The core design studies are being conducted by the CEA with support from AREVA and EDF. Innovative design choices for the core have been made to comply with the GEN IV reactor objectives, marking a break with the former Phénix and...
Mr
Igor Petrov
(JSC “Afrikantov OKBM”)
6/26/17, 2:00 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
The construction of Power Unit No. 4 with the BN-800 reactor plant at the Beloyarsk NPP is the crucial stage in the industrial-scale development of the sodium-cooled fast neutron reactors(SFR).
The activities on the development of the BN-800 reactor plant commenced in1980.
During the period from 1993 to 2005 and later on until the equipment deliveries started, the activities were being in...
Mr
Artem Anfimov
(Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")
6/26/17, 2:00 PM
Safety analysis of BN-1200 RP Unit is performed with account of requirements specified for innovative nuclear technologies including IAEA recommendations.
The following BDBAs are considered within BN-1200 project:
Heat removal accidents with loss of energy supply, failures of active systems for reactor shutdown, failures of normal cooldown system and active components of emergency...
Dr
B.K. Nashine
(Indira Gandhi Centre for Atomic Research, Kalpakkam (T.N.) - India)
6/26/17, 2:20 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Liquid sodium is used as coolant due to its suitable neutronic and thermal properties in fast reactors. Good electrical conductivity of sodium is used for development of electromagnetic devices such as electromagnetic pumps & flowmeters and level probes for use in sodium cooled fast reactors, where conventional devices used in chemical plant cannot be used due to high chemical activity of...
Hiroyuki Ohshima
(Japan Atomic Energy Agency)
6/26/17, 2:20 PM
A numerical simulation system, which consists of a deformation analysis program and three kinds of thermal-hydraulic analysis programs, is being developed in Japan Atomic Energy Agency in order to offer methodologies to clarify thermal-hydraulic phenomena in fuel assemblies of sodium-cooled fast reactors under various operating conditions including fuel deformation. In this paper, we focus on...
Mr
RAGHUPATHY S.
(Indira Gandhi Centre for Atomic Research, Kalpakkam)
6/26/17, 2:20 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Small and large rotatable plugs (SRP & LRP) are provided to facilitate in-vessel handling of core subassemblies using transfe arm. These plugs are rotated during refuelling of the reactor. The control & instrumentation signals and power to various systems / components located on the rotatable plugs are carried by cables and are connectied to their respective control panels located outside....
Mr
Frédéric Payot
(CEA : Commissariat à l’Energie Atomique et aux Energies Alternatives)
6/26/17, 2:20 PM
The CEA, together with the NNC, has carried out a feasibility study with regard to conducting an in-pile test program - the future SAIGA program (Severe Accident In-pile experiments for Gen-IV reactors and the Astrid prototype) - on the degradation of an ASTRID-like fuel in the IGR reactor (Impulse Graphite Reactor operated by NNC). The purpose of the SAIGA program is to qualify the SIMMER...
Ms
Elena Marova
(JSC “Afrikantov OKBM”)
6/26/17, 2:40 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
The project of a power unit with BN-1200 reactor is designed using advanced technical solutions, which define evolution of the fast breeder technology in the field of safety parameters and in the field of technical and economical indicators.
At present there was completed estimation of the BN-1200 project from the point of view of its compliance with the requirements of nuclear energy systems...
Prof.
Toru Obara
(Tokyo Institute of Technology)
6/26/17, 2:40 PM
Burning wave fast reactor is very attractive concept. It is possible to achieve very high burnup using natural uranium or depleted uranium as fuel. It does not need fuel reprocessing facility. This kind of reactors can be categorized into two groups. One is the reactor whose burning wave is moving for radial direction, for example, Traveling Wave Reactor. The other is that whose burning wave...
Dr
Ju-Seong Kim
(Korea atomic energy research institute)
6/26/17, 2:40 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To investigate the fuel cladding chemical interaction for the irradiated metallic fuel, high temperature heating tests were performed. The fuel rod consisting of U-10Zr-5Ce fuel with T92 cladding were irradiated in HANARO reactor. After the irradiation, the fuels was cut into cylindrical specimens, and then the top and the bottom plates of the specimens were put into contact with FC92 and HT9...
Prof.
Zhao-Fei TIAN
(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)
6/26/17, 2:40 PM
In this paper, the graphics interface and parameter modeling real-time simulation software, Jtopmeret, was used to model and simulate the intermediate heat transport system and the steam power conversion system of China Experimental Fast Reactor (CEFR). The two-phase, multi-component models were taken into consideration to simulate the flow and heat transfer of working medium sodium and...
Mr
Suresh Kumar K V
(Department of Atomic Energy, India, Indira Gandhi Centre for Atomic Reaserch, Kalpakkam, Reactor facilities Group)
6/26/17, 2:40 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Fast Breeder Test Reactor (FBTR) has completed 30 years of operation and is relicensed for further operation up to 2018. FBTR has undertaken major upgradation of systems, components and structures to enhance the safety level, based on the operational feedback, maintenance difficulties and obsolescence. Further, post Fukushima, an extensive retrofitting programme is underway to protect the...
Mr
Shigenobu Kubo
(Japan Atomic Energy Agency)
6/26/17, 2:40 PM
This paper describes safety design concept for future sodium-cooled fast reactors (SFRs) in Japan, which is based on the safety design criteria and safety design guidelines under development in the international forum of generation IV nuclear energy systems. The future safety design of SFRs should be advanced taking the feedback of experiences, achievement of existing technology, and...
Prof.
Christophe POINSSOT
(French Nuclear and Alternative Energy Commission)
6/26/17, 3:10 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
In the framework of the successive 1991 and 2006 Waste Management Act, French government supported a very significant R&D program on partitioning and transmutation in fast reactors of minor actinides (MA). This program aimed to study potential solutions for still minimizing the quantity and the hazardousness of final waste, by MA recycling. Indeed, MA recycling can reduce the heat load and the...
Dr
Hideki Kamide
(Japan Atomic Enery Agency)
6/26/17, 3:10 PM
In Japan, we have implemented the development of a sodium-cooled fast reactor from the viewpoint of severe accident measures in order to strengthen safety of a fast reactor since the Great East Japan Earthquake. This paper describes the progress of design study and research and development (R&D) related to safety enhancement and severe accident measures. For the purpose of strengthening of...
Frédéric BERTRAND
(CEA Cadarache)
6/26/17, 3:10 PM
The ASTRID reactor developed by the CEA with its industrial partners, will be used for demonstration of the safety and operability, at the industrial scale, of sodium fast reactors of the 4th generation. Among the goals assigned to ASTRID, one is to improve the safety and the reliability of such reactor (compared to previous sodium-cooled fast reactors). Among the innovations promoted in the...
Mr
E. Vázquez
(National Atomic Energy Commission of Argentina (CNEA)), Mr
Osvaldo Azpitarte
(National Atomic Energy Commission of Argentina (CNEA))
6/26/17, 3:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The International Atomic Energy Agency (IAEA) recently established a Coordinated Research Project (CRP) on “Sodium Properties and Safe Operation of Experimental Facilities in Support of the Development and Deployment of Sodium-cooled Fast Reactors - NAPRO”, to be carried out in the period 2013 – 2017.
Eleven institutions from ten Member States participate in this CRP.
The complete scope of...
Dr
Jonggan Hong
(KAERI)
6/26/17, 3:10 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In Prototype Gen-IV Sodium cooled Fast Reactor (PGSFR), integral once-through type, counter-flow shell-and-tube heat exchanger with straight vertical tubes was adopted for steam generators. Reliable operation of the steam generators has been a key issue through operating experience of foreign sodium cooled fast reactors because it is one of the most important components deciding the plant...
Dr
Vladimir Kriventsev
(IAEA)
6/26/17, 3:15 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
A Coordinated Research Project (CRP) on “Benchmark analysis of EBR-II Shutdown Heat Removal Tests (SHRT)” was launched by the International Atomic Energy Agency (IAEA) in 2012. A series of transient tests were conducted on the EBR-II reactor at Argonne National Laboratory (ANL) to improve the understanding of thermal hydraulics and neutronics of fast reactors. Shutdown heat removal tests...
Ms
Laural Briggs
(Argonne National Laboratory)
6/26/17, 3:25 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In 2012, the International Atomic Energy Agency (IAEA) established a coordinated research project (CRP) on EBR-II Shutdown Heat Removal Tests (SHRT). The objectives of the CRP, which concluded in 2016, were to improve design and simulation capabilities in fast reactor neutronics, thermal hydraulics, plant dynamics, and safety analyses through benchmark analysis of two landmark tests from the...
Dr
Jiri Krepel
(Paul Scherrer Institut)
6/26/17, 3:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Breeding as well as burning capabilities of a reactor operated in the U-Pu or Th-U closed fuel cycle can be estimated from its equilibrium cycle parameters. In this study the equilibrium parameters were simulated for 8 selected fast reactors and both U-Pu and Th-U closed fuel cycles. For simplicity, the fission products were neglected and the reactors were represented only by infinite lattice....
Mr
CLEMENT RAVI CHANDAR SOWRINATHAN
(IGCAR, INDIA)
6/26/17, 3:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
India had constructed and is operating Fast Breeder Test Reactor (FBTR) with Mixed Carbide Fuel, a first of its kind in the world, as driver fuel. Mixed Carbide was chosen as fuel due to its high stability with Pu rich fuel, compatibility with coolant and for its better thermal performance. Being a unique fuel of its kind without any irradiation data, it was decided to use the reactor itself...
Mr
Stephane Vaudez
(CEA)
6/26/17, 3:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In order to prepare the industrial deployment of Sodium Fast Reactor (SFR), a French prototype is envisaged for 2025 (ASTRID: Advanced Sodium Technological Reactor for Innovative Demonstration). Its MOX (mixed oxide) fuels will be produced by a new industrial facility, currently under development and named AFC (for “Atelier de Fabrication des Coeurs”, core fabrication facility).
The...
Dr
Vladimir Kriventsev
(IAEA)
6/26/17, 3:30 PM
Due to the inherent characteristics and robust design of Sodium cooled Fast Reactors (SFR), the core disruptive accident (CDA) is considered a very unlikely event. Nevertheless, to confirm the safety of the reactor, one of the hypothetical scenarios arising from the loss of coolant flow coupled with the failure of the shutdown system, referred to as the Unprotected Loss of Flow (ULOF) accident...
Ms
Barbara Vezzoni
(Karlsruhe Institute of Technology (Germany)), Mr
Wilfred Van Rooijen
(Research Institute of Nuclear Engineering (RINE), University of Fukui, (Japan))
6/26/17, 3:45 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
A Coordinated Research Project (CRP) initiated by the International Atomic Energy Agency (IAEA) aimed to benchmark Shutdown Heat Removal Tests (SHRT) conducted at Experimental Breeder Reactor II (EBR-II). Two SHRT tests (SHRT-17 and SHRT-45R) representative, respectively of Protected Loss of Flow (PLOF) and Unprotected Loss of Flow (ULOF) transients were considered. The SHRT-45R benchmark...
Mr
Francesco Lodi
(University of Bologna)
6/26/17, 3:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Among the numerous numerical methods available for preliminary design verification purposes, the sub-channel one has historically been the reference, thanks to its ability to cover the scale between CFD and system codes which is the one of particular interest for the core designer. Recently, the sub-channel code for liquid metal applications ANTEO+ has been developed by ENEA and a...
Dr
Victor BLANC
(CEA)
6/26/17, 3:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the Basic Design of the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) project, the design margins have to be defined with accuracy. The design criterion considered here is the fuel melting margin during nominal operation conditions, which is given by the melting probability.
Oxide fuel temperature and melting temperature being calculated with...
Mr
Rajan Babu Vinayagamoorthy
(Director (Technical))
6/26/17, 3:50 PM
BHAVINI, a public sector unit under Department of Atomic Energy, is responsible for construction, commissioning and operation of fast reactors in India. Prototype Fast Breeder Reactor (PFBR) which is in advanced stage of commissioning is the forerunner for the second stage of India’s three stage nuclear programme. PFBR is a 1250 MWt (500 MWe), MOX fuelled, sodium cooled, pool type fast...
Andrei Shadrin
(Bochvar Institute)
6/26/17, 3:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Mixed U-Pu used fuel of fast reactors has a high Pu content, high burn-up (50 GW/days*ton and more), and short cooling time (no more than 3 years) as compared with the thermal reactors used fuel. Combined (pyro + hydro) and hydrometalurgy reprocessing technologies are developed in Russian Federation for the close nuclear fuel cycle. These technologies provide reprocessing of used fuel with 1-3...
Ms
Dalin Zhang
(Xi'an Jiaotong University), Dr
Ethan Bates
(TerraPower)
6/26/17, 4:05 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
This paper presents the conclusions of a 4 year benchmark study on the simulation of the EBR-II SHRT-45R experiment. The SHRT-45R experiment was an unprotected loss of flow transient where pump dynamics, natural convection, core and mechanical behavior played a large role in passively and safely limiting the power and temperature rise of the fuel assemblies. Participants from China, Germany,...
Dr
Velusamy Karuppanna Gounder
(IGCAR)
6/26/17, 4:10 PM
The heat generating fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch within a hexagonal sheath forming a fuel subassembly (SA). Due to the compact design, formation of local flow blockage inside the SA is possible. Such blockages are expected to grow gradually and the core monitoring thermocouples which are located at the top of the SA are...
Dr
M. Laura Japas
(CNEA - Argentina)
6/26/17, 4:10 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Sodium densities along the whole liquid-vapor coexistence curve are reanalyzed using the equation proposed by Apfelbaum and Vorob’ev(1). The formulation has built-in the correct behavior for liquid and vapor densities, both at low temperature and in the near-critical region. Thus, it satisfactorily represents the available experimental data in the low and intermediate temperature range, while...
Dr
Kamil Tucek
(European Commission, Joint Research Centre)
6/26/17, 4:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In order to develop the fast neutron systems, three prototypes of the Sodium Fast Reactor, the Gas-cooled Fast Reactor and a heavy liquid metal cooled Accelerator Driven System are studied in Europe: ASTRID (SFR prototype), ALLEGRO (GFR prototype) and MYRRHA (LBE-cooled ADS system related to the ALFRED LFR-demonstrator). The ESNII+ project with its workpackage 7-FUEL SAFETY aims to provide a...
Dr
Stéphanie Cornet
(Nuclear Energy Agency)
6/26/17, 4:10 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Activities related to the fast reactors systems at the Nuclear Energy Agency (NEA) mainly focus on scientific research and technology development needs and are carried out within the Nuclear Science Division. In particular, projects related to the advanced nuclear systems and fuel cycles are carried out through the Working Party of Scientific Issues of the Fuel Cycle (WPFC) and its five...
Mr
JEAN-MARIE HAMY
(AREVA NP)
6/26/17, 4:10 PM
In the frame of the French ASTRID project led by CEA, AREVA NP is in charge of the design studies of the whole Nuclear Island. The conceptual design was completed end of December 2015 with the issuance of a large amount of engineering files (few thousands.
The design of ASTRID intends to cope with GEN IV objectives regarding the new reactor concepts and includes ambitious performances to...
Mr
Partha Sarathy UPPALA
(Indira Gandhi Centre for Atomic Research)
6/26/17, 4:25 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Experimental Breeder Reactor (EBR-II) was a U-Pu-Zr metal-alloy fuelled liquid-metal-cooled fast reactor, extensively used for conducting safety experiments. EBR-II was heavily instrumented to measure sodium flows and temperatures at various locations in the primary circuit including the temperature distribution inside the subassemblies (SA). Several transient tests were conducted on the...
Mr
IURII DROBYSHEV
(VNIIAES JSC)
6/26/17, 4:30 PM
A lot of approaches are considered to increase a marketability of fast breeder reactors producing two products – electricity and exceeding nuclear fuel. To increase a production of exceeding nuclear fuel it is proposed to switch from widely used oxide fuel to carbide, nitride and the densest metallic uranium fuel. In a fabrication chain of the exceeding nuclear fuel a cost of spent nuclear...
Prof.
Christophe POINSSOT
(French Nuclear and Alternative Energy Commission)
6/26/17, 4:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Environmental issues are nowadays a growing concern within most of the public opinion. It is therefore mandatory to propose relevant and qualified assessment of the overall environmental footprint of the different types of energy sources which are envisaged to be implemented. This question is specifically important for nuclear energy which suffers from a poor image in the public opinion due to...
Mr
Aleksandr Trufanov
(SSC RF-IPPE)
6/26/17, 4:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The results of experimental investigations of local velocities for height and radius of the top of the camera in the plane in the direction from the core center to the intermediate heat exchanger and the temperature of the coolant in the upper (hot) chamber, and other elements of the circulation circuit on the integrated water model of the reactor on fast neutrons (scale ~ 1:10) for the...
Mr
Suresh Kumar Kannankara Vasudevan
(IGCAR, Dept. of Atomic Energy, India)
6/26/17, 4:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The advantages of a fast reactor, especially one that uses Uranium-Plutonium Carbide as its fuel is well documented. Irradiation performance assessment of carbide fuels began with experimental irradiations in EBR-II, FFTF, HFR, Rapsodie and Phenix etc. India has the extensive experience with this type of fuel at the Fast Breeder Test Reactor at Kalpakkam that has been operating for over 25...
Dr
Barbara Vezzoni
(Karlsruhe Institute of Technology (KIT)), Mr
MIchael Flad
(Karlsruhe Institute of Technology)
6/26/17, 4:30 PM
The analyses of Hypothetical Core Disruptive Accidents (HCDAs) play a fundamental role in the safety assessment of Sodium Fast Reactors (SFRs). The accident sequence is subdivided into different phases suggested by dominant key phenomena. The Initiation Phase (IP) describes the fatal deviation from nominal operation until the failure of single sub-assemblies (SAs), while the subsequent...
Mr
Nikita Rtishchev
(IBRAE RAN)
6/26/17, 4:45 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In 2012 the IAEA initiated a 4-year coordinated research project (CRP) “Benchmark Analyses of EBR-II Shutdown Heat Removal Tests”, with Argonne National Laboratory serving as the lead technical institution. Nineteen participants from eleven countries were involved in the project. The overall purpose of the CRP was to improve validation of state-of-the-art sodium-cooled fast reactor (SFR)...
Mr
Sergey Porollo
(IPPE)
6/26/17, 4:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Uranium mononitride fuel was used in the fourth and fifth BR-10 reactor core loadings. The total number of irradiated fuel pins was 1250 (660 and 590 fuel pins in fuel loadings IV and V respectively). Most fuel pins were irradiated up to design burnup (8%) without cladding failure.
In addition to standard FAs, some experimental FAs were irradiated in BR-10 reactor. The post irradiation...
Mr
KODANDARAMAN J
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
6/26/17, 4:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
The Indian fast reactor program, which began with the construction of the mixed carbide fuelled Fast Breeder Test Reactor (FBTR) at Kalpakkam, has reached a level of maturity with three decades of operating experience and is stepping into the realm of commercial operations with the construction of Prototype Fast Breeder Reactor (PFBR). The necessary technology for closing the fuel cycle, which...
Mr
Yannick Gorsse
(CEA-Saclay)
6/26/17, 4:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In the framework of the ASTRID Gen4 SFR project, extensive R&D efforts are under way to improve and better validate the SFR thermal-hydraulics codes available at CEA. These efforts include :
- The development and validation of SFR-specific models in CATHARE. Developed at CEA, CATHARE is the reference STH code for French LWR safety studies : SFR developments are being integrated and...
Mr
Christopher Grandy
(Argonne National Laboratory)
6/26/17, 4:50 PM
The FASTER test reactor was designed as part of the U.S. Advanced Demonstration and Test Reactor Options (ADTR) Study in 2015/2016. The ADTR study provided an assessment of advanced reactor technology options and is intended to provide a sound comparative technical context for future decisions concerning these technologies. Point designs for a select number of concepts were commissioned....
Dr
Yasushi OKANO
(Japan Atomic Energy Agency)
6/26/17, 5:35 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
The Generation-IV International Forum (GIF) Task Force completed development of Safety Design Criteria (SDC) for the Generation-IV SFR systems in May, 2013. SDC reflects high level GIF safety and reliability goals (excellence in operational safety and reliability, and reduced likelihood and degree of core damage) and follows GIF basic safety approach (application of defense-in-depth and...
Mr
Ryodai Nakai
(Japan Atomic Energy Agency)
6/26/17, 5:45 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
The Generation-IV International Forum (GIF) Safety Design Criteria Task Force (SDC TF) has been developing a set of safety design guidelines (SDG) to support practical application of SDC since completion of the “SDC Phase I Report” that clarifies safety design requirements for Generation IV SFR systems. The main objective of the SDG development is to assist SFR developers and vendors to...
Mr
Paul Gauthé
(CEA)
6/26/17, 5:55 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
From a general perspective, generation IV (GEN IV) reactors should excel in safety, and as part of a continuous improvement process, provide safety enhancements with respect to GENIII reactors.
GENIII safety objectives are already very ambitious, notably regarding:
- Prevention of the severe accident;
- Mitigation of the severe accident in the frame of the fourth level of defense in...
Mr
Subhash Chander CHETAL
(India)
6/26/17, 6:05 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
to be provided later by the author
Dr
JAEWOON YOO
(Korea Atomic Energy Research Institute)
6/26/17, 6:15 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
Korea Atomic Energy Research Institute (KAERI) is developing Prototype Generation-IV SFR (PGSFR). The first design stage has been completed at the end of 2015 and the preliminary safety information document (PSID) has been issued as a main outcome of the phase. The safety design approach of PGSFR is compliance of defense-in-depth and to enhance the inherent and passive safety design features...
Iurii Ashurko
(IPPE)
6/26/17, 6:25 PM
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
6/26/17, 6:35 PM
Mr
ARUN KUMAR BHADURI
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
6/27/17, 8:00 AM
Fast Breeder Reactors form the second stage of India’s three stage Nuclear Power Programme based on the domestic nuclear resources. Indira Gandhi Centre for Atomic Research (IGCAR) is primarily dedicated for the broad based research & development of sodium cooled fast reactors, fuel cycle and associated technologies.
India is operating a Fast Breeder Test Reactor (FBTR) since 1985, fuelled...
Mr
Yutaka Sagayama
(Japan Atomic Energy Agency)
6/27/17, 8:30 AM
As stated in the “Fourth Strategic Energy Plan”, which was approved by the Cabinet in April 2014, Japan continues to position nuclear energy as a major base-load power source even after the TEPCO’s Fukushima Dai-ichi Nuclear Power Station accident. Its basic policy in the plan is to promote nuclear fuel cycle in terms of the efficient use of resources and reduction in volume and toxic level of...
Dr
JAEWOON YOO
(Korea Atomic Energy Research Institute)
6/27/17, 9:00 AM
The Korea Atomic Energy Commission (KAEC) authorized the R&D action plan for the Advanced SFR (sodium-cooled fast reactor) and the pyro-process to provide a consistent direction to long-term R&D activities in December, 2008. This long-term advanced SFR R&D plan was revised by KAEC in November 2011 in order to refine the plan and to consider the available budget for SFR. The revised milestones...
Mr
Alexander Tuzov
(JSC "SSC RIAR")
6/27/17, 9:30 AM
As early as the exploration of nuclear energy based on the fission of heavy atoms, it became obvious that one of the key conditions for its future wide-scale application is nuclear breeding. For this purpose, in the middle of the last century, the Soviet Union started implementing an experimental infrastructure to develop and construct fast reactors. In a quick period of time the following...
Dr
Tai Asayama
(Japan Atomic Energy Agency)
6/27/17, 10:20 AM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
This paper summarizes ongoing efforts in Japan Atomic Energy Agency on the development of core and structural materials for sodium-cooled fast reactors. For core materials, oxide dispersion strengthened (ODS) steels and 11Cr ferritic steel (PNC-FMS) will be applied to fuel pin cladding and wrapper tube, respectively. As for ODS steel, 9Cr,11Cr-ODS steels have been extensively developed. Their...
Mr
RAGHUPATHY S.
(Indira Gandhi Centre for Atomic Research, Kalpakkam)
6/27/17, 10:20 AM
Prototype Fast Breeder Reactor (PFBR) has two independent and diverse fast acting shutdown systems. The mechanisms that handle Control & Safety Rods (CSR) are called Control and Safety Rod Drive Mechanism (CSRDM). CSRDM & CSR are for start up, control of reactor power, controlled shutdown and SCRAM of the reactor. The mechanisms that handle Diverse Safety Rods (DSR) are called Diverse Safety...
Mr
Michele Frignani
(ANN)
6/27/17, 10:20 AM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
Fast reactors are typically considered for their potential to make optimal use of natural resources or for their potential to minimize the amount and level of nuclear waste. The additional opportunity of fast reactors designed for cogeneration applications (i.e., production of electricity and process heat), which can bring an enormous reduction in CO2-emissions, is made possible by the...
Prof.
Gerald Rimpault
(CEA)
6/27/17, 10:20 AM
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Sodium Fast Reactor design that will be France's Flagship 4th Generation Reactor.
Its innovative core contains many axial and radial heterogeneities (in order to obtain a negative void coefficient) and interfaces that are challenging for current deterministic codes to simulate correctly. Hence there is the need...
Dr
Acacia Brunett
(Argonne National Laboratory)
6/27/17, 10:20 AM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The United States has extensive experience with the design, construction, and operation of a variety of sodium cooled fast reactors (SFRs) over the last six decades. Despite the closure of various facilities, the U.S. continues to dedicate research and development (R&D) efforts to the design of novel experimental, prototype, and commercial facilities. Accordingly, in support of the rich...
Ms
Olga Andrianova
(IPPE JSC “SSC RF –IPPE”, 1, Bondarenko sq., Obninsk, Kaluga reg. 249033)
6/27/17, 10:40 AM
The paper presents the results of a computational and experimental analysis of a systematized and revised series of experiments carried out between 1990-2013 on measurements of absolute fission rate of minor actinides (from 237Np to 245Cm) in different neutron spectra at the BFS-1,2 facilities. A total of 25 critical configurations, i.e., reactor core models with different fuels and coolants...
Mr
Dmitriy Tolstoukhov
(ITCP «PRORYV», Russian Federation)
6/27/17, 10:40 AM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
In the report said about reducing the share of nuclear power generation in the world. In conditions inter-fuel competition highest growth rates show renewables. The key to advancing the development of nuclear energy is to ensure the competitiveness of NPPs whith solving systemic problems. Modern NPPs with LWR in an open NFC, practically exhausted the potential of improving the...
Dr
Vladimir Bobrovskii
(M.N. Miheev Institute of Metal Physics of Ural Branch of Russian Academy of Sciences)
6/27/17, 10:40 AM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Fast neutron irradiation gives rise to rather complex processes developing in the fuel element claddings that lower their technical characteristics and restrict time of safe exploitation. Neutron diffraction studies open up a possibility to monitor them even at a stage of incubation period and thereby to promote development of reliable methods for life expectancy prolongation of the reactor...
Dr
Aydin Karahan
(Argonne National Laboratory)
6/27/17, 10:40 AM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The SAS4A safety analysis code has been extended to include mechanistic and physics-based models of U-Pu-Zr and U-Zr metallic fuel pins. The simulation of various phenomena such as metal fuel component migration, fission gas behavior, clad wastage formation, gas swelling induced axial fuel expansion, in-pin and ex-pin molten fuel relocation, and clad failure models has been significantly...
Mr
FRANCK DECHELETTE
(CEA)
6/27/17, 11:00 AM
At the beginning of the Basic Design phases of ASTRID starting in 2016, the entire fuel handling route has been challenged in order to improve some aspects like availability and investment cost. Especially, studies performed at the end of preliminary design (2010 – 2015) phase show that the availability target will be difficult to obtain with a significant risk of malfunction because of...
Dr
Viktor Dekusar
(Laboratory of Nuclear Fuel Cycle system analysis taking into account National and International tendencies)
6/27/17, 11:00 AM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
The fuel cost component (FCC) of electricity generation is defined as a specific indicator - the cost of 1 kWh of electricity produced. This value is obtained as the levelized (discounted) nuclear fuel cost value, generally beginning with natural uranium procurement and ending with spent fuel management, normalized to the total electric energy generated over the nuclear power plant lifetime....
Mr
Puthiyavinayagam Pillai
(Indira Gandhi Centre for Atomic Research)
6/27/17, 11:00 AM
Dynamic reliability methodologies account for the safety system's time dependent characteristics while estimating the reliability. Time dependence can arise due to interaction of process variables with the hardware and hardware failure on process conditions. Though static reliability models often capture the average behavior and try to make conservative estimates, it is inadequate from a...
Dr
Alexander Sorokin
(Central Research Institute of Structural Materials “Prometey”)
6/27/17, 11:00 AM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Fracture toughness and fracture strain of austenitic steels are the important performance properties, which control serviceability of the components of fast reactors including fuel assemblies. It is known that the above properties decrease under irradiation and thermal ageing. Especially strong decrease of fracture toughness occurs under irradiation accompanied by swelling. It is necessary to...
Mr
Vyacheslav Pershukov
(ROSATOM)
6/27/17, 11:00 AM
This report intended to provide an update on the International research center (IRC) based on the fast sodium research reactor MBIR development. The report will include the proposed IRC structure, key terms of participation, proposed areas for multilateral research, etc. It will also present the R&D possibilities that IRC members will have on the closed nuclear fuel cycle due to the...
Dr
Colby Jensen
(Idaho National Laboratory)
6/27/17, 11:00 AM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The restart of the Transient REActor Test (TREAT) facility provides a unique opportunity to engage the fast reactor fuels community to reinitiate in-pile experimental safety studies. Historically, the TREAT facility played a critical role in characterizing the behavior of both metal and oxide fast reactor fuels under off-normal conditions, irradiating hundreds of fuel pins to support fast...
Mr
RAGHUPATHY S.
(IGCAR, KALPAKKAM)
6/27/17, 11:20 AM
Component handling system deals with the handling of fresh and spent subassemblies (fuel handling) and irradiated primary system components using special flasks (special handling). In FBRs, design of fuel handling machines is very important considering the fact that in-vessel handling is a blind operation due to opacity of sodium and most of the fuel handling operations are carried out...
Dr
VALENTIN RYCHKOV
(EDF R&D)
6/27/17, 11:20 AM
The design of a new reactor is an iterative process. At a design stage, each reactor system may exist in several variants : combined together, these variants give different reactor designs.
Probabilistic risk assessment is a tool that gives a measure (risk, and risk space) that may help to compare different reactor designs. Conservative or macroscopic way to perform probabilistic risk...
Mr
GILLES MATHONNIERE
(CEA)
6/27/17, 11:20 AM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
Fast reactor competitiveness is usually examined by comparing fast reactors and light water reactors (LWRs) LCOE (levelized cost of electricity).
As fast reactors have an investment cost higher than LWRs, their kWh production cost is higher than that of LWRs (with the natural uranium current price) and their competitiveness will thus take place when the increase of the natural uranium cost...
Dr
Mikhail Veshchunov
(IAEA)
6/27/17, 11:20 AM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The main IAEA program implementation tools in the area of fuel engineering are Coordinated Research Projects (CRP), Technical Meetings (TM), Expert Reviews, and NEA-IAEA International Fuel Performance Experiments (IFPE) Database. This report provides information about organization and implementation practices of these activities, and summarizes their major outputs including ongoing CRPs and...
Mr
Tanju Sofu
(Argonne National Laboratory)
6/27/17, 11:20 AM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Under the Reactors Product Line of U.S. DOE’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, 3-D, high-fidelity multi-physics simulation capabilities are being developed to address the needs of designers and analysts in studying advanced, non-water reactor systems in general, and SFRs in particular. Simulation-based High-fidelity Advanced Reactor Prototyping (SHARP) toolkit...
Dr
Armando Miguel Gomez Torres
(Instituto Nacional de Investigaciones Nucleares)
6/27/17, 11:20 AM
AZNHEX is a neutron diffusion code for hexagonal-z geometry currently under development as part of the AZTLAN project in which a Mexican platform for nuclear core simulations is being developed. The diffusion solver is based on the RTN0 (Raviart-Thomas-Nédélec of index 0) nodal finite element method together with the Gordon-Hall transfinite interpolation which is used to convert, in the radial...
Dr
Tatiana Ivanova
(OECD Nuclear Energy Agency)
6/27/17, 11:40 AM
Historic measurements of actinide samples in the Dounreay Prototype Fast Reactor (PFR) are of interest for modern nuclear data and simulation validation. Samples of uranium, neptunium, plutonium, americium, curium, and californium isotopes were irradiated for 492 effective full-power days and radiochemically assayed at Oak Ridge National Laboratory (ORNL) and Japan Atomic Energy Agency...
536.
Equipment cost estimation for pilot demonstration lead-cooled fast-neutron reactor BREST-OD-300
Mr
Nikolay Molokanov
(ROSATOM, JSC “NIKIET”, MEPhI)
6/27/17, 11:40 AM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
One of the main problems in determining the investment in the construction of new nuclear facilities at the design stage is the cost estimation of non-standard equipment. The novelty and lack of experience are the features of early stage of the project. The uniqueness of the projected facilities makes it impossible to use catalogues and price-lists. It is required different approaches to...
Mr
Alexander Kozlov
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 11:40 AM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
At the Institute of Nuclear Materials post irradiation examination has been carried out since BN-600 reactor commissioning to justify safety and reliability of different core elements during routine operation and to search for new ways of extending their service life. The examination is carried out in close cooperation with the design bureau (Afrikantov OKBM), nuclear operator (Beloyarsk NPP),...
Mr
dominique barbier
(CEA)
6/27/17, 11:40 AM
Until the end of the first part of the basic design phase (2017), the ASTRID project has made the choice of studying a power conversion system (PCS) based on a Brayton cycle with nitrogen as coolant. The justification is related to a safety and public acceptance considerations in order to inherently eliminate the sodium-water and sodium-water-air reactions risks. The objective of the studies...
Mr
Pavel Antipin
(JSC “Afrikantov OKBM”)
6/27/17, 11:40 AM
Probabilistic safety analysis (PSA) is a constituent part of range of works aimed at BN power units safety assessment during operation (BN-600 and BN-800 reactors power units), lifetime extension (BN-600 reactor power unit), designing (BN-1200 reactor power unit). PSA reports are part of the document sets required to obtain appropriate Rostechnadzor licenses.
JSC “Afrikantov OKBM” together...
Mr
Venkatesan Arasappan
(Indira Gandhi Centre for Atomic Research)
6/27/17, 1:30 PM
Track 8. Professional Development and Knowledge Management
ORAL
Knowledge Management is the process of creating value from an organization’s tangible and intangible assets and regarded as a significant contributing tool to enhance the performance of organization. Knowledge accumulated over decades of nuclear research, development & operation (organizational memory) have to be preserved and used for the future design, innovations and continued safe...
Mr
Olga Myazdrikova
(Leypunsky Institute for Physics and Power Engineering (IPPE))
6/27/17, 1:30 PM
On the basis of the normative documents requirements on fire safety of nuclear power facilities the build concept and the composition of fire protective system in fast reactors premises with sodium equipment are presented. The main purpose of sodium fire safety system is to protect the technological areas of nuclear power plants with sodium cooled fast reactors from hazards of sodium fire. The...
Mr
Evgenii Marinenko
(Institute for Physics and Power Engineering)
6/27/17, 1:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The main life limiting factor of nitride fuel pins at high burn-up is fuel cladding mechanical interaction (FCMI) leading to strong deformation or even cladding destruction. The consequences of FCMI depend on fuel and cladding swelling rates, cladding creep rate, cladding long-term stress rupture etc. The calculation modelling problem arise from not enough data on nitride out-of-pile...
Mr
Artem Kuznetsov
(JSC “Afrikantov OKBM”)
6/27/17, 1:30 PM
The initial loading of BN-800 is mainly made of the uranium oxide fuel and partially of MOX fuel subassemblies (16% of the total quantity), which were fabricated using both the pellet technology and vibro-packing technology. With account of this specific completing process, such core is called the hybrid core.
The core layout was selected to simplify the future transition from the hybrid core...
Dr
Branislav Vrban
(B&J NUCLEAR ltd.)
6/27/17, 1:30 PM
Under specific transients, fast reactor cores often show significant deviation in their power distribution which leads to spatial instability. As a quantitative indication of these decoupling characteristics, the λ-mode eigenvalue separation has been frequently employed. The physical interpretation of eigenvalue separation provides a measure of the spatial neutronic coupling among various...
Dr
bruno MICHEL
(CEA/DEN/DEC/SESC/LSC)
6/27/17, 1:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the basic design of ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) the GERMINAL fuel performance code is developed in the PLEIADES software environment. In order to improve one dimensional modelling of GERMINAL, a 3D simulation for the SFR fuel pin behavior under irradiation has been proposed.
The 3D model represents a single pellet fragment...
Dr
Petr Dařílek
(VUJE Inc., SK91864 Trnava, Slovak Republic)
6/27/17, 1:50 PM
Status of neutron-physical analysis of ALLEGRO - demonstrator of the gas cooled reactor is characterised at this article.
Benchmarking of existing neutronic codes utilised for PWR analyses mainly, is first task, solved at running projects. As there are available no neutronic experiments with He coolant at fast spectrum, code to code comparison was selected as first stage of validation...
Dr
Robert Jacqmin
(CEA, Cadarache)
6/27/17, 1:50 PM
As part of a bilateral agreement on the study of large axially-heterogeneous oxide-fueled SFR cores, CEA and IPPE have recently performed neutron physics experiments in the BFS facility. The configurations of interest are pancake-shape cores with a split fissile column and a sodium plenum, designed to favor a high inner plutonium conversion ratio and a low sodium void worth. Separate effect...
Dr
Mitsuhiro Aoyagi
(Japan Atomic Energy Agency)
6/27/17, 1:50 PM
Since sodium has high chemical reactivity with oxygen and moisture, sodium fire accident is one of key issues in sodium-cooled fast reactor (SFR) plants when the sodium leaks out of a coolant circuit. In order to evaluate the consequence of the sodium fire event numerically, JAEA has developed sodium fire analysis codes such as SPHINCS and AQUA-SF. This paper describes a PIRT (Phenomena...
Mr
Alexander Kozlov
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 1:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Nowadays austenitic stainless steels are used as a cladding material for BN-600 and BN-800 reactors. Examinations carried out at the end of fuel element service life give the information about cladding state. On the basis of the examination it is necessary: 1 – to determine residual life and 2 – to find the way for its extension.
Extrapolation methods are generally used for the first aspect....
Mr
Georgy Tikhomirov
(NRNU MEPHI), Mr
Vyacheslav Pershukov
(ROSATOM)
6/27/17, 1:50 PM
Track 8. Professional Development and Knowledge Management
ORAL
Nuclear education and training for innovative projects are regarded. National Research Nuclear University (MEPI) history is shown as an example of the university, which has great experience in nuclear education and training, including innovative fast reactor projects. The activity classification and steps of technical specialist training for fast nuclear power engineering are presented. The...
Mr
Roger GARBIL
(European Commission Euratom Nuclear Fission)
6/27/17, 2:10 PM
Track 8. Professional Development and Knowledge Management
ORAL
The European Atomic Energy Community (Euratom) Research and Training framework programmes are benefitting from a consistent success in pursuing excellence in research and facilitating Pan European collaborative efforts across a broad range of nuclear science and technologies, nuclear fission and radiation protection.
To fulfil Euratom R&D programmes keys objectives of maintaining high levels...
Mr
Artem Kuznetsov
(JSC “Afrikantov OKBM”)
6/27/17, 2:10 PM
One of the main objectives for BN-800 development is to master the closed nuclear fuel cycle technologies using the mixed uranium-plutonium (MOX) fuel. The initial loading of BN-800 with the hybrid core mainly made of the uranium oxide fuel includes the limited quantity (16%) of MOX fuel subassemblies fabricated at experimental production facilities of Mayak Production Association and JSC SSC...
Mr
Marc LAINET
(French Alternative Energies and Atomic Energy Commission (CEA))
6/27/17, 2:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
A fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA within the PLEIADES simulation framework. The present main goal of GERMINAL is to meet the needs of the design studies of ASTRID, the future Advanced Sodium Technological Reactor for Industrial Demonstration in France.
Recent works have been conducted to improve the modelling of different physical mechanisms...
Dr
Luke Lebel
(Institut de Radioprotection et de Sûreté Nucléaire)
6/27/17, 2:10 PM
The original sodium fast reactor concepts date back to the 1950s and 1960s, and there were large programs in France, Japan, Russia, and the United States in the 1970s and 1980s to design and build commercial-scale SFRs. Many of these programs were abandoned in the 1990s, but a considerable amount of work was done prior to that in order to demonstrate the concepts, and to support the safety...
Mr
Xingkai Huo
(China Institute of Atomic Energy)
6/27/17, 2:10 PM
China Experimental Fast Reactor (abbr. CEFR) is a pool-type sodium-cooled fast reactor in China Institute of Atomic Energy (abbr. CIAE), with a thermal power of 65MW and an electric power of 20MW. The construction started in 2000 and the first criticality was reached in July 2010. On December 15th 2014, CEFR reached full power for the first time and was successfully operated for 72 hours....
Mr
Vyacheslav Shikhalev
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 2:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Electrical potential testing which is a primary nondestructive testing method is used at JSC "INM" hot cells as an incoming inspection of spent BN-600 and BN-800 reactor fuel elements.
Electrical resistivity curves demonstrate the level of the fuel element defectiveness and help to work out a cladding dismantling plan for further post irradiation materials examination of the cladding problem...
Mr
Andrey Boldyrev
6/27/17, 2:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The advanced version of code BERKUT designed for mechanistic modelling of oxide and nitride single fuel rod behavior under normal and accidental conditions of liquid metal cooled fast reactor operation, is under development at IBRAE RAN during the last five years in frame of “Codes of new generation” project included into the “BREAKTHROUGH” (or “PRORYV”) project. The code models are grounded...
Dr
Konstantin Mikityuk
(Paul Scherrer Institute)
6/27/17, 2:30 PM
Track 8. Professional Development and Knowledge Management
ORAL
An increasing number of countries are opting for new nuclear energy as an important step towards economic development and environmental protection. According to the IAEA, electricity from nuclear energy may triple by 2050 as evidenced in the report IAEA-RDS-1/33; therefore, the projected use of this carbon-free technology will require many new nuclear engineers and scientists. In addition,...
Prof.
Claubia Pereira
(Universidade Federal de Minas Gerais)
6/27/17, 2:30 PM
A GFR core model with 100 MWt was evaluated using three different fuel compositions: conventional (U, Pu)C and two reprocessed fuels with transuranic (TRU) (Pu, Am, Np, Cm). One reprocessed by UREX+ technique and spiked with depleted uranium, (U,TRU)C, and the other reprocessed by the same technique but spiked with thorium, (Th,TRU)C. The reprocessed fuel came from a PWR standard fuel (33,000...
409.
OPERABILITY VALIDATION OF FUEL PINS WITH CLADDINGS MADE OF EK164-ID STEEL IN THE BN-600 REACTOR
Mr
Sergey Belov
(JSC “Afrikantov OKBM”)
6/27/17, 2:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To ensure the increased fuel burn-up in the BN-600 and BN-800 reactors, EKA64-ID steel is going to be used as a fuel rod cladding material because it has bigger index of radiation resistance (swelling and creeping) in comparison with the used ChS68-ID steel. To introduce this steel, an irradiation examination of experimental FSAs is needed to be performed. Owing to the irradiation examination,...
Mr
Marti Jeltsov
(KTH Royal Institute of Technology)
6/27/17, 2:30 PM
Pool-type configuration of LFR (lead-cooled fast reactor) primary systems allows for simple and economic reactor design solutions. However, partially-filled heavy liquid pools pose seismic safety concerns related to sloshing. Violent sloshing can lead to structural failures, gas entrapment and potential core voiding. Seismic isolation systems are used to reduce the mechanical stresses in...
427.
A proposal for a pan-European E&T programme supporting the development and deployment of ALFRED
Ms
Sara Bortot
(KTH)
6/27/17, 2:50 PM
Track 8. Professional Development and Knowledge Management
ORAL
The entire process of implementation of a nuclear program relies on the availability of qualified expertise and of national infrastructures providing the general framework for the smooth execution of regulated activities. Building an innovative reactor, besides the challenges related to the advanced nuclear technology and the important aspects of costs and financing, implies also the...
Dr
Lizhen Tan
(Oak Ridge National Laboratory)
6/27/17, 2:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Optimized Grade 92 has been developed at Oak Ridge National Laboratory in support of the USA Sodium-cooled Fast Reactor program. Composition modification and processing optimization successfully achieved the development of optimized Grade 92 with desired microstructures for superior properties. A variety of properties have been assessed for optimized Grade 92, which include tensile, creep,...
Mr
Kazuo YOSHIMURA
(Japan Atomic Energy Agency)
6/27/17, 2:50 PM
To maintain sodium level inside reactor vessels above cores is essential to keep core-cooling for sodium leakage accidents in loop-type sodium-cooled fast reactors. In the loop-type prototype fast reactor Monju which has three primary heat transport systems (PHTSs), a single coolant leakage accident in a PHTS has been taken into account as a design basis accident (DBA). On the other hand, it...
Prof.
Iulian Golovchenko
(Russian Federation)
6/27/17, 2:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To guarantee an inherent safety in advanced BN-reactors the breeding ratio of its active core (BRC) must have the meaning of BRC ≥ 1,0. It could be reached in heterogeneous oxide-metal cores of various types in use of metal uranium as the fertile components in the proportion of MOX:U ≈ 2:1.
We obtained the experience of manufacturing the fertile columns of various types from the metal...
Prof.
EDMUNDO DEL VALLE GALLEGOS
(Instituto Nacional de Investigaciones Nucleares (On Sabbatical Leave from IPN-Mexico))
6/27/17, 2:50 PM
The AZTLAN Platform project is a Mexican national initiative led by the National Institute for Nuclear Research of Mexico, which brings together nuclear institutions of higher education in Mexico: the National Polytechnic Institute, the National Autonomous University of Mexico and the Autonomous Metropolitan University, in an effort to take a significant step towards positioning Mexico, in the...
Mr
karl vulliez
(CEA, DEN, SDTC, Laboratoire d’Etanchéité, 30207, Bagnols Sur Cèze France.)
6/27/17, 3:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project, the CEA Sealing Laboratory with its partner TECHNETICS (TGF) was involved to propose a new concept of rotating plug seals to replace the commonly used liquid-metal seals. An innovative combination of static, dynamic and inflatable seals in silicone rubber ensuring double...
Prof.
Augusto Gandini
(Sapienza University of Rome)
6/27/17, 3:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
**Recent and potential advances of the Heuristically based Generalized Perturbation Theory (HGPT) methodology are discussed:**
- *The subcriticality monitoring method*
Basing on the HGPT methodology applied to subcritical systems, a procedure is described for the online monitoring of the subcriticality level of ADS reactors with minimal interaction with the plant normal operation.
The...
Dr
Alessandro Alemberti
(Ansaldo Nucleare SpA)
6/27/17, 3:30 PM
Since 2012 the Lead Fast Reactor provisional System Steering committee (LFR-pSSC) of Generation IV International Forum (GIF) has developed a number of top level activities with the aim to assist and support member countries developments of Lead Fast Reactor technology.
The current full members (MoU signatories) of the GIF-LFR-pSSC are: EURATOM, JAPAN, the RUSSIAN FEDERATION and the REPUBLIC...
Prof.
Gerald Rimpault
(CEA)
6/27/17, 3:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The use of the Iterated Fission Probability method in the Monte Carlo code Tripoli4® gives credit to deterministic codes such as ERANOS for calculating βeff. The asset of Tripoli4® is the possibility to get a better representation of experimental cores, especially the R2 experimental core which exhibit more experimental canals for hosting large fission chambers. The BERENICE measurements...
Dr
Hyungmo Kim
(KAERI)
6/27/17, 3:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
A separate effect test facility called SELFA (Sodium thermal-hydraulic Experiment Loop for Finned-tube sodium-to-Air heat exchanger) using liquid sodium and air as operating fluids has been developed. SELFA is one of the requisite sodium thermal-hydraulic test facilities within the framework of STELLA (Sodium Test Loop for Safety Simulation and Assessment) program, which is indispensible for...
Dr
Luciano Cinotti
(Hydromine Nuclear Energy S.a.r.l.)
6/27/17, 3:50 PM
LFR-AS-200 is under development by Hydromine in cooperation with ENEA. LFR stands for Lead-cooled Fast Reactor, AS stands for Amphora-Shaped, referring to the shape of the inner vessel and 200 is the electrical power in MW. The project has been carried out by a team of engineers who had participated to the construction of SPX1.
The strengths of the LFR-AS-200 are safety, simplicity,...
Mr
Sergey Rukhlin
(JSC “Afrikantov OKBM”)
6/27/17, 4:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To purify primary sodium in the advanced BN-1200 reactor plant, a purification system with cold traps has been used that are located in the reactor vessel (in-built purification system). Such decision has excluded external communications of the auxiliary system with radioactive sodium and respectively a possibility that sodium will outflow to compartments outside the reactor.
The sizes of...
Prof.
Qunying Huang
(CnINEST)
6/27/17, 4:10 PM
Lead-based reactor is one of the most promising nuclear energy systems for Generation-IV Accelerator Driven subcritical System (ADS) and reactors. Chinese Academy of Sciences (CAS) had launched a project to develop ADS and lead-based fast reactor technology since 2011. China LEAd-based Reactor (CLEAR) was selected as the reference reactor, which was performed by Institute of Nuclear Energy...
Dr
Gennady Manturov
(PhD)
6/27/17, 4:10 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Designing of neutronics characteristics of fast reactor cores and fuel cycle requires to use certified and qualified sets of computer codes and nuclear data. The calculation codes should be related to the modern state of computational techniques. The used nuclear constants should be adequate to the most reliable evaluations, adopted in modern libraries of evaluated nuclear data.
The paper...
Mr
david plancq
(CEA)
6/27/17, 4:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Within the framework of the French 600MWe Advanced Sodium Technological Reactor for Industrial Demonstration project (ASTRID), a Gas Power Conversion System (PCS) based on a Brayton cycle is studied. This innovative option has never been implemented in any Sodium Fast Reactor and is mainly justified by safety and acceptance considerations in inherently eliminating the sodium-water and...
Mr
Vadim Lemekhov
(JSC NIKIET)
6/27/17, 4:30 PM
BREST-OD-300, an innovative natural-safe fast reactor, is being developed as a pilot and demonstration prototype for the base commercial reactor facilities of future nuclear power with a closed nuclear cycle.
Coolant in the reactor facility is lead, the layout of the primary circuit is integral, the reactor vessel material is multilayer metal concrete. The reactor core design uses mixed...
Jaeseok Heo
(Korea Atomic Energy Research Institute)
6/27/17, 4:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In this research, uncertainty analyses for multiple safety parameters were performed for Unprotected Loss of Flow (ULOF) for the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) by using the PArallel Computing Platform IntegRated for Uncertainty and Sensitivity analysis (PAPIRUS). The objective of the global uncertainty analysis is to evaluate all safety parameters of the system in the...
Prof.
Gerald Rimpault
(CEA)
6/27/17, 4:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
An OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) has been formed under the NSC/WPRS/EGUAM and is currently undertaking preliminary studies after having specified a series of benchmarks.
The incentive for launching the SFR-UAM task force comes from the desire to utilize current understanding of...
Mr
Aleksei Sedov
(NRC "Kurchatov Institute")
6/27/17, 5:30 PM
Fast Gas Reactor BGR-1000 with thermal power of 2 GW is cooled with high-pressure helium (16 MPa), heated in the core from 350 to 750oC. In a steam generator of the power conversion system the thermal power is transferred to the SCW-coolant of secondary circuit, which goes to the turbine with pressure of 30 MPa and temperature of 650oC. Reactor core contains Fuel Assemblies (FA) having...
Dr
Thierry GERVAIS
(AREVA)
6/27/17, 5:30 PM
Abstract
--------
Since 2015, **AREVA and CEA** teams decided to launch yearly industrial tests of MOX pellets with an adapted GEN III design in the **MELOX** plant, to prepare the future manufacturing of MOX fuels bundle for Astrid reactor.
First campaign (2015) of tests was dedicated to demonstrate the feasibility of this manufacturing at half industrial scale; Main modifications...
Ms
Sandra Bogetic
(University of California at Berkeley)
6/27/17, 5:30 PM
This project investigates the safety of the optimal core design for the RBWR-TR – a reduced moderation BWR with a high transuranic (TRU) consumption rate. This design is a variant of the Hitachi RBWR-TB2, which arranges its fuel in a hexagonal lattice, axially segregated seed and blanket regions, and fits within a standard ABWR pressure vessel. The RBWR-TR eliminates the internal axial blanket...
Mr
YOSHIKAZU YAMADA
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
Researchers at Japan Atomic Energy Agency (JAEA) have proposed the transmutation of minor actinides (MAs) by both fast reactors (FRs) and accelerator driven system (ADSs) as a way to contribute significantly to the reduction of the volume and the potential radiotoxicity of radioactive wastes. In order to achieve this goal, it is important to introduce a fully automated and remote operation...
Prof.
Bruno Merk
(University of Liverpool)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
Invention and innovation with regards to nuclear reactor development can be described with the concept of developments in s-curves. This view is taken to identify the problems of nuclear development. Following this, the request are formed for the definition of demand driven objectives. The future objectives should follow the UN sustainable development goals. The key words to form the vision of...
Mr
S Sikorin
(The Joint Institute for Power and Nuclear Research SOSNY of the National Academy of Sciences of Belarus)
6/27/17, 5:30 PM
For many years, Russian researchers have developed and tested a high density, high temperature U-Zr-C-N fuel for potential application in different types of reactors, including fast reactors. As part of this effort, reactor tests have been performed to low burnup. However, reactor-testing data is still needed at high burnup to confirm the optimal performance of the fuel. The SM-3 reactor,...
Dr
David Grabaskas
(Argonne National Laboratory)
6/27/17, 5:30 PM
A mechanistic source term (MST) calculation attempts to realistically assess the transport and release of radionuclides from a reactor system to the environment during a specific accident sequence. The U.S. Nuclear Regulatory Commission (NRC) has repeated stated its expectation that advanced reactor vendors will utilize an MST during the U.S. reactor licensing process. As part of a project to...
Mr
Yong YANG
(China Institute of Atomic Energy)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
1.radioactive harmfulness of the spent fuel
2.capability of MA burning in 600 MWe FBR
3.a study of nuclear energy system scenario
4.summary
Dr
James Sienicki
(Argonne National Laboratory)
6/27/17, 5:30 PM
Advanced energy conversion using the supercritical carbon dioxide (sCO2) Brayton cycle has been under development at Argonne National Laboratory (ANL) for over twelve years. It has been shown to enable the SFR capital cost per unit output electrical power ($/kWe) or Levelized Cost of Electricity (LCOE) to be significantly reduced improving SFR economics (a U.S. DOE SFR goal) and eliminating...
Dr
David Grabaskas
(Argonne National Laboratory)
6/27/17, 5:30 PM
Beginning in 2015, a project was initiated to update and modernize the probabilistic safety assessment (PSA) of the GE-Hitachi PRISM sodium fast reactor. This project is a collaboration between GE-Hitachi and Argonne National Laboratory (Argonne), and funded in part by the U.S. Department of Energy. Specifically, the role of Argonne is to assess the reliability of passive safety systems,...
Mr
Randall Fielding
(Idaho National Laboratory)
6/27/17, 5:30 PM
Under the US Fuel Cycle Technologies program Advanced Fuels Campaign metallic fuel has been chosen as a leading candidate for fast reactor transmutation fuels. Significant losses were seen in an earlier attempt to incorporate americium into a metallic fuel, although the majority of the losses were likely not caused by the volatility of americium, these concerns have persisted. A furnace has...
Dr
Matthew Bucknor
(Argonne National Laboratory)
6/27/17, 5:30 PM
The U.S. Nuclear Regulatory Commission has stated that mechanistic source term (MST) calculations are expected to be required as part of the advanced reactor licensing process. A recent study by Argonne National Laboratory has concluded that fission product scrubbing in sodium pools is an important aspect of an MST calculation for a sodium cooled fast reactor (SFR). To model the phenomena...
Mr
Vadim Alexandrovich Shurupov
(JSC “SSC RF – IPPE”)
6/27/17, 5:30 PM
At high flowrates the «drift» of magnetic field characterized by the criterion Rem = μ0σvD can be revealed in the readings of the electromagnetic flowmeters if it’s magnetic field is insufficiently extensive. The modeling of high range flowmeters presented involves using a small on scale transducer sample as compared to full scale flowmeter maintaining similarity of measuring section and...
Mr
Yaroslav Kotov
(National Recearch Centre "Kurchatov Institute")
6/27/17, 5:30 PM
The work contains results of calculation studies of neutron physics characteristics of the fast modular sodium reactor core, in which fuel assemblies without casing with heterogeneity inside fuel assemblies are used. Metal fuel (U-Pu-Zr) is the most advantageous fuel of all known challenging fuel types for a fast sodium reactor regarding neutron characteristics. It enables obtaining the...
Dr
Igor Suslov
(ITC "PRORYV" Project)
6/27/17, 5:30 PM
“Point kinetics” approximation is widely used in reactor justification for calculation of transient and emergency modes in the first place. The point kinetic model is used as the base model for Russian DINROS, GRIF, SOKRAT-BN software programs used for safety justification of fast reactors. Its popularity is explained by its relative simplicity and physical transparency (possibility to...
Mr
Jakub Lüley
(Slovak University of Technology)
6/27/17, 5:30 PM
Presented paper assess standard reactivity effects, as coolant void effect and Doppler effect, of the power scale Gas cooled Fast Reactor (GFR 2400) in a comprehensive manner by application of the perturbation theory. To achieve high validity of the results the conventional SCALE 6 system and adapted computational scheme (ACS) are utilized. The ACS is based on standard computational package...
Dr
Bernard GUILLOU
(SEIV)
6/27/17, 5:30 PM
Authors: René-Paul BENARD, Bernard GUILLOU (SEIV)
Christoph DÖDERLEIN (CEA)
The ASTRID reactor is the French demonstrator for Generation IV sodium cooled fast reactors and needs as such to respond to challenges in the qualification of innovative components and materials. Considering its role as R&D platform for the fast reactor line to come, ASTRID will be endowed with a set of...
Mr
FREDERIC CHANTECLAIR
(French Alternative Energies and Atomic Energy Commission (CEA))
6/27/17, 5:30 PM
Abstract FR 17
Track 1. Innovative Fast Reactor Designs
ASTRID reactor: design overview and main innovative options for Basic Design
F. Chanteclair(a) in association with all the ASTRID industrial partners
(a) French Alternative Energies and Atomic Energy Commission (CEA), F- 13 108 Saint Paul Lez Durance, France
Sodium-cooled Fast Reactors (SFR) is one of the Generation IV...
Christopher Matthews
(Los Alamos National Laboratory)
6/27/17, 5:30 PM
The fuel performance code BISON has recently been extended to simulate U-Zr and U-Pu-Zr metallic fuel rods irradiated in the US sodium cooled fast reactor EBR-II. By introducing fuel and clad specific material models, the backbone provided by the MOOSE/BISON software architecture has allowed rapid development of metallic fuel capabilities. Zirconium based fuels present unique challenges due to...
Mr
Stéphane BEILS
(AREVA NP)
6/27/17, 5:30 PM
In case of a severe accident inside a sodium-cooled fast reactor, corium interacts with many materials along its way towards the core catcher. Once deposited, corium can also interact with protective and / or sacrificial material. Among those materials, refractory ceramics like zirconia are credible candidates due to their high fusion temperature. Through CFD methodology, calculations have...
Mr
Rajan Babu Vinayagamoorthy
(Director (Technical))
6/27/17, 5:30 PM
Prototype Fast Breeder Reactor (PFBR) consists of Primary Sodium Circuit (PSC), Secondary Sodium Circuits (SSC), Safety Grade Heat Removal Circuits (SGDHRC) and Steam-Water circuit. The principal material of construction for sodium piping circuits is austenitic SS316LN/SS304LN.
Manufacturing of thin and big bore piping with tight tolerances along with the high distortion in stainless...
Mr
SUDHIR MISHRA
(BHABHA ATOMIC RESEARCH CENTRE, INDIA)
6/27/17, 5:30 PM
Sudhir Mishra1, Amrit Prakash1, K. B. Khan1 , Vivek Bhasin2
Radiometallurgy Division, 2Nuclear Fuels Group,
Bhabha Atomic Research Centre,
Mumbai- 400 085, India.
E-mail: sudhir@barc.gov.in
Abstract
Mixed (U0.3, Pu0.7)C fuel is the driver fuel for Fast Breeder Test Reactor (FBTR ) at Kalpakkam, India. This fuel is being fabricated at Radio metallurgy Division, Bhabha Atomic...
Ms
Svetlana Barsanova
(Joint Stock Company «Institute of Nuclear Materials»)
6/27/17, 5:30 PM
During fuel element operation changes in structure and physical and mechanical properties of the claddings are induced by irradiation and other factors. In particular, there are such changes as swelling, embrittlement, softening and corrosion damages. To predict cladding limit state it is necessary to know the changes occurred. In particular, it is important that cladding mechanical properties...
Dr
Konstantin Mikityuk
(Paul Scherrer Institut)
6/27/17, 5:30 PM
Calculational analysis of the unprotected loss of flow (ULOF) accident in a Generation-IV SFR, featuring a low-void core design, shows that the chugging sodium boiling regime in the core could last for several hundred seconds during the accident. While in the case of the traditional positive-void SFR core the sodium boiling onset
is almost immediately followed by the power run-away, fuel...
Mr
Krishnamurti Natesan
(Argonne National Laboratory)
6/27/17, 5:30 PM
Sodium Fast Reactor (SFR) is one of the leading advanced reactor concepts that would provide a low-carbon energy option to a diverse U.S. power sources. Nuclear energy releases zero carbon emissions during electricity production, and thus is essential in reducing CO2 emissions from the U.S. power sector. SFR also supports other possible missions, including recycling of used fuel for closing...
Mr
Michael Orlov
(Private institution «Innovation and technology center for the «PRORYV» project»)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
Due to the growing population of Earth, the development of a full-scale nuclear power industry is becoming an increasingly challenging task in the 21st century and onwards. The Breakthrough («Proryv») Project is focused on inherently safe fast reactors which are expected to resolve, for a first time, the economic competitiveness problems of the nuclear power sector. In order to develop a...
Dr
Seyed Mohammad Mirvakili
(AEOI), Dr
Zohreh Gholamzadeh
(AEOI)
6/27/17, 5:30 PM
Molten salt reactors were designed and operated at 1960s. The subcritical accelerator driven MSRs are being considered recently. In the present work, accelerator driven homogeneous subcritical core configuration was Modelled using MCNPX code. The composition of NaF-BeF2-ThF4-TRUF4 and NaF-233UF4-ThF4-TRUF4 was selected as the fuel loaded inside a 58×60 cm cylindrical core respectively. NaBF...
Dr
Velusamy Karuppanna Gounder
(Indira Gandhi Center for Atomic Research)
6/27/17, 5:30 PM
To handle a station black-out (SBO) event, sodium cooled fast reactors are equipped with passive systems to remove decay heat, which do not require external power source. The duration of SBO can extend up to a week. Decay heat removal in FBTR, depends on natural convection, driving flow through the core subassemblies and inter-wrapper spaces. The relatively low decay heat and the extended...
Dr
Michael Benson
(Idaho National Laboratory)
6/27/17, 5:30 PM
A major factor limiting the lifetime of U-Zr based fuel is fuel-cladding chemical interactions (FCCI). As the fuel is burned, fission product lanthanides (Ln) interact with the Fe-based cladding, causing thinning of the cladding wall and eventual breach of the cladding. In order to extend the lifetime of the fuel in reactor, FCCI must be controlled. Palladium has been shown to be a promising...
Mr
Kirill Shutko
(N.A. Dollezhal Research and Development Institute of Power Engineering)
6/27/17, 5:30 PM
Abstract
Once-through type steam generator (SG) is designed for BREST-OD-300 reactor unit. There is the steam overheating zone in the upper part of long-length heat exchange tubes. Consequently, under service conditions SG tubes to be exposed to three corrosion media – liquid lead (primary coolant), pressurized water, and superheated steel at temperatures in the range 350-505 °C, pressure...
Dr
Evgeniya Nikitina
(Institute of High Temperature Electrochemistry)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
The present work is aimed at the study of the 12Х18Н10Т steel corrosion in the molten LiCl-KCl eutectic, which contains different proportions of CeCl3, NdCl3 and UCl3.
The CeCl3 and NdCl3 concentrations varied within the interval of 0.2-5.0 mol.%, and the UCl3concentration varied within the interval of 1.0-2.5 mol.%. The temperature of the experiments was 500 0C. The composition of the melts...
Mr
IURII SHVETSOV
(Private institution «Innovation and technology center for the «PRORYV» project»)
6/27/17, 5:30 PM
The problem of decay-heat removal from a shutdown reactor is still pending and Fucushima accident proved it. The complexity of this problem grows with the increase reactor power.
High power reactors with sodium and lead coolants were analyzed and compared in terms of decay -heat removal using 3D thermo-hydraulic calculations of reactor cooldown.
Two DHRS designs are compared that differ...
Mr
RAGHUPATHY S.
(Indira Gandhi Centre for Atomic Research, Kalpakkam)
6/27/17, 5:30 PM
The core degradation due to Anticipated Transients Without Scram (ATWS) has to be practically eliminated as the fast reactor core is not in its most reactive configuration during normal operation. The ATWS events can lead to early and large release of radioactivity. Deterministic demonstration of dispersal of fuel to avoid further core compaction after initiation of large scale core damage is...
Mr
Lev Kochetkov
(Alexeevich)
6/27/17, 5:30 PM
The initial idea of potential nuclear fuel breeding originated in the USA and the first success in development of fast reactors designed for implementation of this idea was achieved there. With a very small delay, similar studies started in the USSR; however, that was the place where fast reactor development reached its peak. The chief scientific supervisor of these research studies in the...
Dr
Matthew Denman
(Sandia National Laboratories)
6/27/17, 5:30 PM
With the advent of the use of Probabilistic Risk Assessments (PRAs) for safety analysis of Light Water Reactors (LWRs) in the 1970s, the SFR community used PRA as a tool which can demonstrate the safety of SFR designs while avoiding the pitfalls associated with an over-reliance on highly conservative safety requirements. Throughout the 1970s, 80s, and 90s, the US compiled sodium reactor...
Mr
Puthiyavinayagam Pillai
(Indira Gandhi Centre for Atomic Research)
6/27/17, 5:30 PM
The idea of using small specimens for mechanical testing had actually originated in the nuclear industry to cater to the irradiation material testing and reactor surveillance programs. Small or miniaturized specimens ensure efficient use of available irradiation volume in nuclear reactors, reduce uncertainty in irradiation parameters due to flux and temperature variations and also reduce...
Mr
RUDOLF ALEXAKHIN
(INSTITUTION «ITC «PRORYV» PROJECT»)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
The development of nuclear power engineering with closing of a fuel cycle and the use of fast reactors must ensure a higher level of ecological safety of the population and the environment. The highest ecological effect is achieved by recycling of spent fuel and isolation of long-lived radionuclides (90Sr, 137Cs and 99Тс) and transmutation of 99% of americium.
In normal operation of CNFC...
Dr
Alexander Salyulev
(Institute of High Temperature Electrochemistry)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
Pyroelectrochemistry is one of the most prospective approaches for spent nitride nuclear fuel (nitride SNF) reprocessing. It includes the anodic dissolution of the SNF pellets into the molten LiCl-KCl eutectic with the subsequent electrochemical separation of U, Pu, Np, Am from other constituents. Physical-chemical properties of such complex melts are still insufficiently studied.
The...
Dr
Konstantin Mikityuk
(Paul Scherrer Institut)
6/27/17, 5:30 PM
To improve the public acceptance of the future nuclear power in Europe we have to demonstrate that the new reactors have significantly higher safety level compared to traditional reactors. The ESFR-SMART project (European Sodium Fast Reactor Safety Measures Assessment and Research Tools) aims at enhancing further the safety of Generation-IV SFRs and in particular of the commercial-size...
Prof.
Deokjung Lee
(Ulsan National Institute of Science and Technology)
6/27/17, 5:30 PM
Small Modular Sodium-cooled Fast Reactor (SM-SFR) was developed in UNIST as a breeder reactor with the target of ultra-long cycle operation. The depletion analysis and quasi-static reactivity balance analysis were performed to see its inherent safety in the neutronics point of view. In this study, the inherent safety evaluation is performed in the thermal-hydraulic point of view by using...
Mr
Yoshihiro Sekio
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
For the development of nuclear core materials, especially fuel cladding tube, in sodium-cooling type fast breeder reactor, void swelling suppression is one of the most important issues to keep the dimensional stability in reactor. A large number of theoretical and experimental investigations on void swelling behavior have been carried out, and void swelling directly depends on the diffusion of...
Mrs
Natalia Glushkova
(Joint Stock Company «Institute of Nuclear Materials»)
6/27/17, 5:30 PM
Austenitic stainless steel has been used as a standard material for BN-600 fast reactor claddings for many years. High-temperature strength is one of the advantages of austenitic steels over ferritic-martensitic ones. Nevertheless, corrosion damages, radiation-induced swelling, creep, embrittlement, and strength reduction are topical problems for claddings made of austenitic steels. In this...
Mr
Kiichi Suzuki
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
Japan Atomic Energy Agency has developed mixed plutonium-uranium oxide (MOX) fuel fabrication technologies in large-scale and fabricated MOX fuel assemblies for experimental fast reactor “JOYO” and prototype fast reactor “MONJU” at Plutonium Fuel Production Facility (PFPF) since 1988. Low density pellet is adopted as MONJU fuel. For the low density pellet fabrication in large-scale, various...
Mr
Sureshkumar KV
(RFG, IGCAR)
6/27/17, 5:30 PM
Operational life of Fast Breeder Test Reactor (FBTR) is limited by the grid plate life. An irradiation experiment was carried out in FBTR to determine changes in the mechanical properties of specimens of grid plate material at the desired low fluence irradiation conditions. Based on the analyses of these experiments and flux measurements at the grid plate location, the residual life of FBTR...
Mr
Balija Sreenivasulu
(IGCAR)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
Advanced fuels forms need to be developed for use with the evolving nuclear fuel cycles. The fabrication of sphere-pac fuel pins that employ microspheres of U,Pu mixed oxide (MOX) or microspheres containing the oxides of Minor Actinides (MA) prepared through the internal gelation process are particularly relevant in this context. Since the sol-gel process used in the fabrication of these...
Dr
Matthias Vanderhaegen
(Federal Agency for Nuclear Control)
6/27/17, 5:30 PM
In Belgium, the research center SCK•CEN is planning to build a lead alloy-cooled fast reactor as part of an ADS facility. And Whilst the Belgian Regulator, i.e. the Federal Agency for Nuclear Control - FANC, has experience with the licensing and control of PWRs, there was little to no experience with these less-common innovative reactor types. For this reason a prelicensing project was...
Dr
Kazumi IKEDA
(Mitsubishi FBR Systems, Inc.)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
This paper shows a feasibility study of transmuting minor-actinide (MA) by MA-zirconium hydride, (MA, Zr)Hx in radial blanket region of a fast reactor and a plan of technology development for the MA target. The feature of this concept is that it has a great potential of transmutation and can be used in proven fast reactors, but naturally requires research and development.
The proposed (MA,...
Dr
Victor Dekusar
(Dekusar)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
In a time of the existence of the national nuclear program in the framework of the weapons and civil complex it has been accumulated and continues to accumulate a significant amount of plutonium.
The isotopic vector of plutonium produced in reactors varies strongly depending on the type of reactor, fuel burnup and the time elapsed since the moment of unloading it from the reactor before ...
Mr
Sergei Terentev
(JOIN STOCK COMPANY «SIBERIAN GROUP OF CHEMICAL ENTERPRISES»)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
Further effective development of fast energy engineering could not be realized without strategy of nuclear fuel cycle closure. Throughout the realization of this strategy combined PH-technology of mixed nitride uranium-plutonium fast reactor spent fuel is proposed.
Full-fledged affination extractive-crystallizng platform was created for hydrometallurgical pro-cesses adjustment and above...
Dr
Nak Hyun Kim
(Korea Atomic Energy Reasearch Institute)
6/27/17, 5:30 PM
In PGSFR (prototype-gen IV sodium-cooled fast reactor), two kinds of DHRSs (decay heat removal systems) are employed for emergency decay heat removal during a loss of normal heat sink accident, which are ADHRS (active decay heat removal system) and PDHRS (the passive decay heat removal system). The ADHRS is a safety-grade active system, which is comprised of two independent loops with a single...
Dr
Sandra POUMEROULY
(EDF R&D)
6/27/17, 5:30 PM
Innovative Sodium-cooled Fast Reactors (SFRs) are currently investigated in the ESNII+ European project. The goal of the WP6 “Core safety” of this project is to support the development of the ESNII roadmap as well as the implementation of the ESNII deployment strategy and licensing of the ESNII systems by identifying the experimental and theoretical R&D activities which are necessary for...
Dr
David Louie
(Sandia National Laboratories)
6/27/17, 5:30 PM
This paper describes the progress of the CONTAIN-LMR sodium physics and chemistry models to be implemented into MELCOR 2.1. It also describes the progress to implement these models into CONTAIN2. In the past three years, the implementation included the addition of sodium equations of state and sodium properties from two different sources. The first source is based on the previous work done...
Mr
Nikolay Maslov
(National Research Centre "Kurchatov Institute" National Research Nuclear University MEPhI (Moscow Engineering Physics Institute))
6/27/17, 5:30 PM
The task undertaken in the report is to increase inherent safety of the fast reactor with a sodium coolant of type BN-800 due to considering the possibility of using an innovation fuel assemblies with mixed uranium-plutonium carbide fuel in form of coated particles. Fuel assemblies with pellet MOX fuel and fuel rods are directly replaced by microspherical mixed (U,Pu)C-fuel. Calculation...
Irina Portnykh
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 5:30 PM
One of the main issues of fast reactors is to improve their economic efficiency. Nowadays austenitic stainless steel ChS-68 is used as a state material for BN-600 reactor claddings ensuring damage doses up to 87 dpa. Post irradiation examination results show the residual life of fuel elements with possible maximum damage dose up to 92-95 dpa corresponding to fuel burn-up to 12-13 % FIMA. At...
Dr
Viktor Alekseev
(JSC "SSC RF-IPPE")
6/27/17, 5:30 PM
The report observes the behavior of the system sodium - oxygen - stainless steel with regard to the sodium cooled circulation loop. Computational and theoretical analysis of mass transport of corrosion products in the channels of non-isothermal circuit in view of chemical interaction of the components of steel with oxygen in sodium, including the reaction of sodium oxide with chromium in...
Mr
Aleksandr Sorokin
(SSC RF-IPPE)
6/27/17, 5:30 PM
As results of neutronics and thermal physical investigations of reactor installation BN-HT type with heat rating 600 MW have shown that there is a principal possibility to provide demanded parameters of a high-temperature fast reactor for production of a considerable quantity of hydrogen, for example, on the basis of one of thermochemical cycles or a high-temperature electrolysis with high...
Dr
María Luppo
(Argentina Atomic Energy Commission)
6/27/17, 5:30 PM
The Time-Temperature-Transformation (TTT) diagram of an ASTM A335 P92 steel (9CrMoWVNNb) has been established starting from an austenitization temperature of 1050 °C. Isothermal transformation was carried out at temperatures from 625 up to 775 °C taking 25 °C intervals, using a high resolution dilatometer. Only two state fields (i.e., austenite and ferrite + carbides) were observed, in full...
Mr
Alexander Denisov
(Deputy Director International Business Sosny R&D Company), Mr
Vincent Reynaud
(CHAMPALLE SAS)
6/27/17, 5:30 PM
The presentation describes the author’s experience in design, manufacturing and installation of equipment used in Mixed Uranium – Plutonium fuel pellet fabrication in Russia. The key features of mixed uranium-plutonium oxide and nitride powders are described, as well as their influence on main process (furnaces, presses) and auxiliary (gloveboxes) equipment design. Technical solutions for...
Mrs
NATHALIE GIRAULT
(IRSN)
6/27/17, 5:30 PM
The JASMIN project was launched in the frame of the 7th Framework Programme (FP) of the European Commission (EC). It was inspired by the Gen-IV target of designing innovative reactors that intrinsically prevent severe accidents from occurring or drastically reduce their consequences. One of the main objectives of the 7th FP was the enhancement of the current capability of analysis of severe...
Mr
Igor Peshkichev
(RFNC-VNIITF)
6/27/17, 5:30 PM
Implementation program of fast reactors in nuclear power engineering provides for the use of new types of nuclear fuel, in particular nitride. RFNC-VNIITF in cooperation with VNIINM develops models and codes for the simulation of physical and chemical processes for the purpose of software development and implementation of nitride mixed uranium-plutonium fuel fabrication technology. The main...
Mr
Shun Hirooka
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
Designing nuclear fuels and simulating their irradiation behaviors in a reactor require modeling and formulation of a variety of fundamental properties. The property study of uranium-plutonium mixed oxide (MOX) as fast reactor fuels still requires further investigation because of the diverse parameters and the technical obstacles of plutonium operation.
Young’s modulus of MOX pellets...
Dr
Kyungho Yoon
(Korea Atomic Energy Research Institute)
6/27/17, 5:30 PM
The PGSFR core is a heterogeneous, uranium-10% zirconium (U-10Zr) metal alloy fuel design with 112 assemblies: 52 inner core fuel assemblies, 60 outer core fuel assemblies (FA), 6 primary control assemblies (CA), 3 secondary control assemblies, 90 reflector assemblies (RA), and 102 B4C shield assemblies (SA). The core is designed to produce 150 MWe with an average temperature rise of 155 ℃....
Dr
Tomoko Ishizu
(Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))
6/27/17, 5:30 PM
Mechanical consequences which might be caused by core disruptive accidents (CDAs) are one of the major concerns in FBR safety. Once a severe re-criticality occurs, core materials are vaporized creating a CDA bubble which consists of fuel vapor, steel vapor and fission gases. Rapid expansion of the CDA bubble drives a sodium slug of the upper plenum and threatens integrity of the shielding...
Ms
Olga Myazdrikova
(Institute for Physics and Power Engineering named after A.I. Leypunsky” (IPPE))
6/27/17, 5:30 PM
A description is given of a physico-mathematical model of the processes that occur in the sodium circuit with a variable flow cross-section in case of a water leak into sodium. The application area for this technique includes a possibility to analyze consequences of this leak as applied to sodium-water steam generators in fast neutron reactors.
Hydrodynamic processes that occur in the sodium...
Ms
Inga Makeyeva
(RFNC-VNIITF)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
There exist different variants of organizing the closure of nuclear fuel cycle (CNFC) depending on fast reactor type, fuel types, station or centralized allocation of closed nuclear fuel cycle stages. Many processes and engineering solutions used for implementation of chosen technologies for re-processing spent fuel are little-studied. One of the ways to verify and estimate engineering...
Dr
Sergey Starikov
(Nuclear Safety Institute of the Russian Academy of Sciences)
6/27/17, 5:30 PM
Description and prediction of behavior of nuclear engineering materials under operating conditions is one of the challenging goals in actual materials science. To solve this problem, when the restricted experimental information is only available (e.g. for the new kinds of nuclear fuel), the most perspective method seems to be theoretical description based on multiscale approach. In this case...
Mr
Chihyung Kim
(Korea Advanced Institute of Science and Techology)
6/27/17, 5:30 PM
The breed-and-burn fast reactor (B&BR) is a unique concept of fast reactor, which can breed the fissile fuels and use the bred fuels in situ. Thanks to this characteristic, the fuel utilization in a B&BR can be extremely high and even the spent nuclear fuel of a B&BR can be re-used as a fuel to spawn the next generation B&BR after appropriate reprocessing or reconditioning. In this paper, a...
Dr
María Luppo
(Argentina Atomic Energy Commission)
6/27/17, 5:30 PM
This work introduces new results on the transformation behavior and microstructural evolution of ASTM A335 P92 steel under continuous cooling conditions (CCT). The first results were already reported and stored in the INIS database under the report number INIS-AR-C--1704.
The material was austenized at 1050 ºC and afterwards cooled down at controlled rates (300, 200, 140, 120, 100, 90, 70,...
Dr
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
6/27/17, 5:30 PM
Numerical and experimental investigations of seismic response behavior of the air heat exchanger (AHX) of prototype fast breeder reactor (PFBR) were carried out for operating basis earthquake (OBE), safe shutdown earthquake (SSE) and beyond design basis earthquake conditions. For the numerical study, a finite element model consisting of AHX header and connecting tubes were developed using...
Dr
Takashi Takata
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
As a collaboration on the field of advanced reactor modeling and simulation in Civil Nuclear Energy Research and Development Working Group (CNWG) between Japan Atomic Energy Agency (JAEA) and Sandia National Laboratory (SNL), information exchange of sodium combustion modeling and experimental data has been carried out.
In the collaborative work, a benchmark analysis of Surtsey spray...
Mr
Boris Hombourger
(Paul Scherrer Institut (PSI), Switzerland; École Polytechnique Fédérale de Lausanne (EPFL), Switzerland)
6/27/17, 5:30 PM
Reactors able to operate in a Breed-and-Burn fuel cycle can operate at equilibrium with minimum fissile input and fuel processing without actinides separation, making them particularly attractive. Historically, the concept has essentially been considered for solid-fuel fast reactors, in particular to sodium-cooled fast reactors. Their performance in breed-and-burn is however limited by the...
Mr
Pavel Maslov
(SSC RF-IPPE)
6/27/17, 5:30 PM
MBIR is a 150 MWt multipurpose research sodium cooled fast reactor, designed for a broad range of experimental studies in various lines of research. Vibropacked MOX-fuel with relatively high plutonium weight content (under 40%) is accepted as the standard fuel for MBIR reactor facility. At the same time, there is a principal possibility of using alternative types of fuel in this reactor: both...
Mr
Andrei Glazov
(Institution “Innovation and Technology Center by “PRORYV” Project”, State Atomic Energy Corporation “Rosatom”)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
Dynamic developing of modern nuclear industry demands meeting the following requirements: improved safety, reduced capital costs, radioactive waste management issues, independence of limited resources.
Efficiency of uranium resources used in "Brest" reactors based on a closed fuel cycle is about 160 times higher than for VVER, RBMK reactors, which allows to stop searching for new deposits...
Mr
Jean-Baptiste GENIN
(CEA, DEN)
6/27/17, 5:30 PM
The OSCAR-Na code has been developed to calculate the mass transfer of corrosion products and related contamination in the primary circuit of sodium fast reactors (SFR). Indeed, even if fuel cladding corrosion appears to be very limited, the contamination of the reactor components plays an important role in defining the design, the maintenance and the decommissioning operations for SFR....
Dr
William Carmack
(Idaho National Laboratory)
6/27/17, 5:30 PM
Research and development activities on fast reactor fuels in the US are focused on their potential use for actinide transmutation in future sodium fast reactors. As part of this application, there is a desire to demonstrate a multifold increase in burnup potential.
A number of fuel design innovations are under investigation with a view toward significantly increasing the burnup potential of...
Dr
Staffan Qvist
(LeadCold AB)
6/27/17, 5:30 PM
A major focus of the design of modern fast reactor systems is on inherent and passive safety. Inherent safety means that the reactor design is such that the plant remains in a safe condition solely on the basis of the laws of nature; these laws ensure that all performance characteristics remain within safe bounds under all conceivable circumstances. The definition of passive safety is broader,...
Dr
Xue-Nong Chen
(KIT, IKET)
6/27/17, 5:30 PM
This paper investigates the possibility of a boiling water cooled traveling wave reactor, which can improve the natural uranium utilization of a Light Water Reactor (LWR) by umpteen times. The high density variation of boiling water through the core is favourable to fission at the lower part of the core and to the fuel breeding at the upper part of the core. This is the case in a low pressure...
Mr
Evgenii Kinev
(Institute of Nuclear Materials)
6/27/17, 5:30 PM
A large number of post irradiation examinations of the state of spent fuel element composition have been carried out for more than ten years of successful operation of BN-600 core of the third 01M2 modification. The paper aims to substantiate operating capacity of standard and certain experimental oxide fuel kinds with service life characteristics increase, in particular, burn-up depth...
Dr
María Luppo
(Argentina Atomic Energy Commission)
6/27/17, 5:30 PM
The microstructural stability of ferritic-martensitic heat resistance steels is mainly controlled by the thermal stability of precipitates that are able to retard the growth rate of subgrains. The welded zones appear to be a weak region compared to the base material (BM) and creep rupture takes place in the intercritical or the fine-grained heat affected zones (ICHAZ and FGHAZ).
In the...
Mr
Ignas Mickus
(LeadCold Reactors)
6/27/17, 5:30 PM
SEALER (SwEdish Advanced LEad Reactor) is a small (8 MWt) lead-cooled fast reactor operating on 19.9 % enriched UO2 fuel. It is designed for commercial production of electricity and heat for off-grid consumers and is intended to function as a nuclear battery for up to 30 years. The reactor features a very small temperature gradient over the core to reduce the degrading process of structural...
Mr
Mikhail Ivochkin
(JSC NIKIET, MOSCOW/RUSSIA)
6/27/17, 5:30 PM
As part of the PSA level 1 with BREST-OD-300 reactor the following main tasks have been solved:
- selection and grouping of initiating events. List of IE was formed as a result of the analysis (including specific local impact);
- success criteria (SC) for safety systems and functions. In the frame of this task several deterministic calculations were performed;
- analysis of accident...
Mr
Gennady Kolotkov
(V.E. Zuev Institute of Atmospheric Optics SB RAS)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
In the paper, we consider the gas-aerosol radioactive emissions and theoretically justify the possibility of remote detection of increased radioactivity in air emissions from the nuclear reactor BN. The comparative analysis of injected radionuclides into the atmosphere from nuclear power plant with advanced fast neutron reactor is carried out. On example of Beloyarsk nuclear power plant, the...
Mr
Dmitry Blagodatskykh
(Nuclear Safety Institute (IBRAE RAN))
6/27/17, 5:30 PM
In order to perform calculations for determination of zones of radioactive contamination within a particular urban area one needs to take into account the inhomogeneous wind field and essentially anisotropic turbulence.
According to the state-of-the-art trends in applied computational meteorology a robust CFD model has been developed in the IBRAE RAN in frame of “Codes of new generation”...
Dr
Andrey Lizin
(Russian Federation)
6/27/17, 5:30 PM
The salt compositions based on the fluorides of alkaline elements (Li, Na, K) have all the necessary properties for the reliable molten-salt reactor operation. Currently available information on the molten salts properties allows to make some recommendations for the choice of the carrier salt for the fast MSR of the different types. The high solubility of the actinide and lanthanide fluorides...
Mr
Roman Sadovnichiy
(JSC “SSC RF – IPPE”)
6/27/17, 5:30 PM
Up-to-date technology of lead-based coolants is now founded mainly on the paramount importance of oxygen addition to the coolant assuring corrosion resistance of structural steels.
In the early stage of HLMC technology development, oxygen content was monitored by coolant sampling and analysis. Later on, more efficient methods of control using electrochemical sensors with solid...
Dr
Alexey Krylov
(Nuclear Safety Institute of Russian Academy of Sciences)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
SIBYLLA code is intended for calculation of the radionuclides content in water and bottom sediments of water bodies undergoing radioactive contamination during normal operating conditions or accidents at the nuclear facilities. Also SIBYLLA enables to calculate the doses resulted from use of the water-bodies including water-supply. The code contains set of models for water bodies of different...
Dr
Meimei Li
(Argonne National Lab)
6/27/17, 5:30 PM
This paper presents the results of sodium compatibility of the base metal and weldment of optimized Grade 92 steel recently developed in the United States for applications in advanced sodium-cooled fast reactors. Optimized Grade 92 (Fe-9Cr-0.5Mo-2W-V,Nb) is a variant of commercially available Grade 92 ferritic-martensitic steels with tighter control of chemistry and thermo-mechanical treatment...
Mr
Vladimir Pastukhov
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 5:30 PM
Radiation-induced swelling of claddings is one of the factors limiting service life of fast reactor fuel assemblies. Hydrostatic weighing and transmission electron microscopy are conventional porosity investigation methods.
Hydrostatic weighing is advantageous in terms of the determination radiation porosity integral characteristics, specifically cladding dimensional change after operation...
Mr
Chang-Gyu PARK
(Korea Atomic Energy Research Institute)
6/27/17, 5:30 PM
A once-through steam generator(SG) in SFR(Sodium-cooled Fast Reactor) coverts the sub-cooled feedwater to superheated steam by transferring heat from the IHTS(Intermediate Heat Transport System) sodium to water/steam and provides superheated steam during normal power condition. It is a heat exchanger as well as structural barrier between liquid sodium and water/steam and thus is regarded as...
Mr
David Montagnier
(AREVA NP), Mr
Dominique Villani
(AREVA NP), Mr
Gilles Rodriguez
(CEA), Mr
Julien Large
(VELAN SAS), Mr
Marc Gosset
(AREVA NP), Mr
Martin Delmas
(VELAN SAS), Mr
Nicolas Crepin
(VELAN SAS)
6/27/17, 5:30 PM
In the framework of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project, the VELAN Company is involved to propose a concept of isolation valve to guaranty the confinement of the reactor block in case of severe accident scenario. An innovative and compact design for the isolation sodium valve was developed. Following the basic design phase studies on the...
Dr
María Luppo
(Argentina Atomic Energy Commission)
6/27/17, 5:30 PM
In this contribution we address the behavior of precipitated second phases during the first minutes of holding in the austenite phase field for an ASTM A335 P91 steel.
It is well known that two main families of precipitated particles are present in this steel after a standard manufacturing process that includes, as final stages, normalizing and tempering, i.e., M23C6 carbides (M = Cr, Fe,...
Mr
FENGLONG WANG
(CHINA INSTITUTE OF ATOMIC ENERGY,BEIJING,CHINA)
6/27/17, 5:30 PM
Confinement including containment and primary vessel are barriers of radioactive gas containing.To select the appropriate confinement leakage rate can ensure the pool-type sodium-cooled fast reactor operating safety.In the paper,large pool-type sodium-cooled fast reactor was the object of research.The impact of different primary vessel and containment leakage rate to radioactive material...
Dr
Yun HU
(China Institute of Atomic Energy)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
The sustainable development of nuclear energy calls for the maximization of uranium utilization and, meanwhile, the minimization of the waste produced. The fuel cycle mode and its key parameters have a great influence to the deployment of nuclear energy and the generation of high-level waste. In this paper, a sensitivity analysis is made on the influence of out-of-core residence time and the...
Dr
Victoria Shvetsova
(Central Research Institute of Structural Materials “Prometey”)
6/27/17, 5:30 PM
The present report represents the study results of mechanisms of fracture and embrittlement of austenitic steels of 18Cr-9Ni and 18Cr-10Ni-Ti grades after long term neutron irradiation at high temperatures. The effect of irradiation temperature, irradiation time and neutron dose is considered on the fracture strain and fracture mechanisms.
It has been found in the present research that long...
Mr
Rajan Babu Vinayagamoothy
(BHAVINI, Dept of Atomic Energy, Kalpakkam)
6/27/17, 5:30 PM
BHAVINI is constructing Prototype Fast Breeder Reactor (PFBR), forerunner of FBRs, a 500 MWe sodium cooled, pool type, mixed oxide (MOX) fueled reactor at Kalpakkam. Presently PFBR is in the commissioning phase. The reactor has three main heat transport circuits namely primary sodium, secondary sodium and steam-water system. The Primary sodium Pump and Intermediate Heat exchanger housed inside...
Mr
Igor Konovalov
(National Research Nuclear University "MEPhI")
6/27/17, 5:30 PM
The atomistic models of the swelling, creep, gas release, and nitride fuel decomposition are presented.
The models were verified on the results of nitride fuel elements irradiation in the Russian fast reactors BR-10, BOR-60 and BN-600.
At temperatures <1150 °C nitride fuel operate under athermal radiation processes that provide the best performance of the fuel element.
At high...
Dmitry Dzama
(Nuclear Safety Institute of Russian Academy of Science)
6/27/17, 5:30 PM
A new approach for assessment of radiation situation outside industrial sites of objects at radiation risk has been being developed in the last few years. This approach is based on performing of multiple calculations using real time series of weather condition parameters. A standard conservative estimation assumes that the meteorological parameters are constant. This assumption increases the...
Mr
Mikhail Baryshnikov
(Head of Back-End Departement)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
1. Introduction
2. NFC in Dual-Component Nuclear Power System
3. Advantages of Dual-Component Power System
4. Reducing RW amount going to disposal
5. Format of commercial proposal
6. Status of Russian nuclear infrastructure
7. Conclusions
Mr
Nikolay Molokanov
(ROSATOM, JSC “NIKIET”, MEPhI)
6/27/17, 5:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
POSTER
The computer model for the economic assessment of Proryv Project (REM) was developed as a result of work in the field of simulation of technical and economic indicators.
REM is designed for supporting managerial decision-making during analyze of building NPP with thermal and fast reactors.
The targets of REM are noted, functional opportunities and technical demands are...
Dr
Giacomo Grasso
(Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))
6/27/17, 5:30 PM
The LFR-AS-200 is a 200 MW(e) Lead Fast Reactor (LFR) standing on simplicity to target the objective of representing a commercially viable option for an innovative Small Modular Reactor (SMR). To fulfil its envisaged role, which is particularly meaningful for multi-units sites, the design has to enhance the safety performances; this is achieved by exploiting the relevant favourable intrinsic...
Dr
Kyoichi Morimoto
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
In uranium-plutonium mixed oxide (MOX) fuel fabrication, the mitigation of specifications on fuel design is considered from a viewpoint of improvement of economic efficiency. The pellet density of the MOX fuel for fast reactors is one of the important specifications in the fuel design and it fluctuates with changes in the properties of raw material powders. As the one of the mitigations of...
Mr
Igor Volkov
(Russian Federal Nuclear Center - All-Russia Research Institute of Technical Physics)
6/27/17, 5:30 PM
Lead-cooled fast reactors are promising direction in the development of nuclear energy because of opportunities to ensure their safety and security. Efforts are underway to develop lead-cooled fast reactors BREST-OD-300 and BREST-1200 in Russia. Nitride fuel is expected to use at the core of these reactors. High density of this fuel gives an opportunity to create an core with the breeding...
Mr
Mikhail Kriachko
(Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")
6/27/17, 5:30 PM
During the reactor operation a continuous generation of the radioactive isotope of hydrogen – tritium – takes place. Tritium is formed in nuclear reactions: fission of the fuel and interaction of neutrons with nuclei of some elements contained in the fuel, structural materials and coolant. Tritium has a great penetrating ability and migrates through the technological media. Thus it gets into...
Mr
Mikhail Belonogov
(RFNC-VNIITF named after academ. E.I. Zababakhin)
6/27/17, 5:30 PM
The growing importance of nuclear energy in the overall balance calls for the further improvement of existing nuclear reactors. However, it is equally important that other reactor types are also considered. The report represents the concept of fast molten salt reactor, neutron-physical and thermo-hydraulic calculations for several core models. It also presents the analysis of different core...
Mr
Mikhail Kriachko
(Joint Stock Company "State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering named after A. I. Leypunsky")
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
One of the main objects of fast reactor nuclear fuel cycle radiation safety is fuel assembly handling. In case of closed nuclear fuel cycle fresh fuel assemblies will be produced from regenerated uranium and plutonium.
Uranium-232 is produced and accumulated in fuel assemblies during the irradiation. One of the U-232 decay products is Tl-208 which emits high energy gamma radiation. In...
Dr
Vladimir Krotov
(Institute of High-Temperature Electrochemistry UB RAS)
6/27/17, 5:30 PM
The cathode crystalline UO2–ThO2 (30-50 mol/ %), UO2-PuO2 (6, 42 and 72 mol. %), UO2-ZrO2 (0.1 – 98 mol. %) deposits, were formed. The electrolyte - melt: (NaCl-KCl)-UO2Cl2-MeCl4, where MeCl4 = ThCl4, PuCl4, ZrCl4. The influence of the MeCl4 concentration in the (NaCl–KCl)–UO2Cl2–MeCl4 melt, the initial electrolysis current density, the temperature, and the electrolysis duration on the average...
Ms
Maria Tarasova
(National research nuclear University "MEPhI")
6/27/17, 5:30 PM
Modern development of nuclear power industry is closing of nuclear fuel cycle. That is possible when fast neutron reactors is used. An attractive fuel for this type of reactor is nitride nuclear fuel. However, the widespread use of a nitride nuclear fuel encounters by problems of its manufacturing and, in particular, during the sintering of the finished powder material. So for the manufacture...
Dr
Anton Filanovich
(Ural Federal University)
6/27/17, 5:30 PM
Nuclear fuel based on mixture of thorium dioxide ThO2 with uranium or plutonium is perspective for many types of breeder reactors, e.g. liquid metal cooled fast breeder reactors (LMFBR), advanced heavy water reactors (AHWRs), gas cooled reactors (HTGR), etc. [1]. Effective and safe usage of these fuels requires information on its thermal and mechanical properties. In the case of PuxTh1-xO the...
Mr
Oleg Golosov
(Joint Stock Company "Institute of Nuclear Materials")
6/27/17, 5:30 PM
High radiation-resistant ferritic-martensitic steels are prospect materials for fast reactor cores. Chromium ferritic-martensitic steel 12Cr-13Mo-2Nb-B-V (EP-450) was successfully used as a shroud tube material for BN-350 reactor fuel assemblies and is still used for BN-600 and BN-800 reactors. It is expected to use ferritic-martensitic steel EP-450 for BN-1200 reactor shroud tubes and...
Dr
Taku Matsumoto
(Japan Atomic Energy Agency)
6/27/17, 5:30 PM
Am-bearing oxide fuel is considered as the fuel candidate for Fast Reactor to reduce the amount of high level radioactive waste. Thermo-physical properties of oxide fuel such as thermal conductivity and diffusion coefficient are very sensitive to the change of O/M ratio. Am is one of high produced minor actinide in irradiated nuclear fuel and its dioxide ($AmO_{2-x}$) has higher oxygen...
Dr
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
6/27/17, 5:30 PM
During Core Disruptive Accident (CDA) in a pool type SFR, primary sodium from hot pool is expelled into the top enclosure, which is vented to reactor containment building (RCB). Sodium coming in contact with oxygen and moisture undergoes combustion and forms sodium oxide / sodium peroxide and hydrogen releasing large amount of heat. The phenomenon of sodium combustion in the form of pool fire...
Prof.
Valeri Smolenski
(Institute of High-Temperature Electrochemistry UB RAS)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
Pyrochemical separation processes in molten salt media have been proposed as a promising option in the future nuclear fuel cycle. The major steps of these processes include the electrorefining or reductive extraction of the recovering actinides in molten chloride/liquid metal systems and for recovery of minor actinides from spent fuel or high level radioactive liquid wastes. The goal of these...
Dr
Nicolas Stauff
(Argonne National Laboratory)
6/27/17, 5:30 PM
Advanced transmutation fuels are being developed for Sodium-cooled Fast Reactors (SFRs) with reduced chemical interaction between the fuel and cladding and higher burnup achievable. Different diluent materials such as Zirconium, MTZ (5Mo-4.3Ti-0.7Zr), with addition of Palladium are considered, together with Cr-coating inside the cladding. The use of advanced transmutation fuels was assessed in...
Dr
Mikołaj Oettingen
(AGH University of Science and Technology, Faculty of Energy and Fuels, Department of Nuclear Energy)
6/27/17, 5:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
POSTER
The closed nuclear fuel cycle belongs to the most promising options
for the efficient usage of the nuclear energy resources with the full recycling of the long-lived transuranic elements. However, it can be implemented only in fast breeder reactors of generation IV. The paper shows our methodology applied to the analysis of lead-cooled fast reactor equilibrium fuel cycle with the application...
Dr
Yann DE CARLAN
(SRMA, CEA Saclay, Université Paris-Saclay, 91191 Gif-sur-Yvette Cedex, France)
6/27/17, 5:30 PM
CEA develops new austenitic and ODS alloys to limit the swelling and withstand very high doses. In this study, 10 Austenitic Stainless Steels with different content of phosphorus, nickel, silicon, titanium and niobium were elaborated and irradiated with iron ions at 600°C in several metallurgical conditions. Different effects on void swelling were observed by Transmission Electron Microscopy...
Mr
Marti Jeltsov
(KTH Royal Institute of Technology)
6/27/17, 5:30 PM
Lead-cooled fast reactor (LFR) is one of most attractive innovative reactor design considered for research and development by the Generation IV International Forum (GIF). The major advantages of LFRs are related to the use of heavy liquid metal coolant (lead or lead-alloy). However, there are still pending safety issues that need resolution. Steam generation tube leakage and/or rupture...
Mr
Vladimir Tsygvintsev
(Joint Stock Company “Institute of Nuclear Materials”)
6/27/17, 5:30 PM
Operation of BN fast reactor structural and fuel materials under hard irradiation and at high temperatures leads to significant irreversible changes in material structure.
X-ray diffraction analysis is a common physical method for materials testing and condition monitoring. Different techniques help to determine crystal phase composition, form, internal stress, crystal preferred orientation...
Prof.
Yonghee Kim
(Korea Advanced Institute of Science and Technology)
6/28/17, 10:20 AM
This talk is concerned with feasibility and challenges for a self-sustainable fast-spectrum SMR (Small Modular Reactor), which can be operated without any refueling and reprocessing during the whole plant lifetime of ~50 years. For a competitive and proliferation-resistant fast-spectrum SMR, long-life core designs are reviewed and a compact SMR design is introduced and its design features and...
Dr
Giacomo Grasso
(Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))
6/28/17, 10:40 AM
content to be provided by the author soon
Dr
Staffan Qvist
(LeadCold AB)
6/28/17, 11:00 AM
the title and content to be provided by author soon
Dr
NATHALIE REYNIER TRONCHE
(CEA, Nuclear Energy Division, RadioChemistry and Processes Department), Ms
emilie buravand
(CEA MARCOULE)
6/28/17, 1:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Dissolution experiments undertaken on irradiated fuel pins from sodium fast reactors (SFR) date back to the 80s at the French Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA). They were operated in different workshops and laboratories, using different experimental conditions.In order to regain then extend the knowledge on SFR MOX treatment and recycling for 4th generation...
Prof.
Valery Strizhov
(Nuclear Safety Institute)
6/28/17, 1:30 PM
In frame of Breakthrough project the system of codes of a new generation is being developing for justification of operational characteristics and safety of the NPP with sodium, lead and lead-bismuth coolants utilizing closed fuel cycle.
Use of the code system by design and industry organizations ensure reduction of uncertainties by the use of precise multi-scale models and more detailed...
Mr
Ivan Zverev
(JSC “Afrikantov OKBM”)
6/28/17, 1:30 PM
One of the most important criteria of successful NPP functioning is ensuring personnel and population radiation safety by defense in depth safety barrier system. Primary coolant and reactor gas radioactivity depends on condition of fuel pins, claddings of which can lose their leaktightness during operation due to various reasons (factory fault, changing of irradiation conditions). That is why,...
Dr
Hual-Te Chien
(Argonne National Laboratory)
6/28/17, 1:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In a sodium-cooled fast reactor (SFR), an under-sodium viewing (USV) system will be essential for real-time monitoring of core operation and/or in-situ inspection and repair of components. The USV system must be capable of operating in the high-temperature, high radiation, and highly corrosive environment of SFRs. Argonne National Laboratory (ANL) has successfully developed ultrasonic...
Mr
SURESH KUMAR K.V
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARECH)
6/28/17, 1:30 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
The Fast Breeder Test Reactor (FBTR) is sodium cooled, loop type fast reactor commissioned in the year 1985. It is a research reactor with an evolving core with a unique Pu/U carbide fuel. The reactor has continued to provide valuable experience to improve its performance figure year after year. FBTR has been operated at different power level up to 27.3MWt/5.8MWe over the last thirty years,...
Prof.
Leonid Bolshov
(Nuclear Safety Institute of the Russian Academy of Sciences)
6/28/17, 1:30 PM
L.A.Bolshov, V.F.Strizhov, D.A. Klinov, A.A. Kamaev, V.V.Lemekhov, A.V.Moiseev, S.F.Shepelev, B.A.Vasiliev
The approaches to assurance and justification of safety of the new generation of fast liquid metal reactors with sodium and heavy coolants that are currently being developed in Russia are presented.
The accepted safety concept deals with some aspects including:
• Assurance of...
Dr
Kamil Tucek
(European Commission, Joint Research Centre)
6/28/17, 1:50 PM
The Generation-IV International Forum Lead-cooled Fast Reactor (LFR) provisional System Steering Committee has developed a set of Safety Design Criteria (SDC) dedicated to LFRs. The objective of the LFR SDC is to present a set of reference criteria for the design of systems, structures, and components of LFR systems with the aim of achieving the safety goals of the Generation-IV reactor...
Mr
Francois Baque
(CEA)
6/28/17, 1:50 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
In Service Inspection of the sodium cooled fast reactor prototype ASTRID leads to a large R&D effort for selecting, developing and qualifying ultrasonic techniques and tools.
Several ultrasonic transducers are developed and tested: TUSHT model (CEA), TUCSS model (AREVA) both based on piezoelectric material, and Electro Magnetic Acoustic Transducers (EMAT, CEA). Each type of transducer...
Prof.
ZhiGang ZHANG
(Harbin Engineering University), Prof.
ZhiJian Zhang
(Harbin Engineering University)
6/28/17, 1:50 PM
With the closed fuel cycle strategy, China develops the fast reactor and advanced reprocessing technology, which supports the sustainable development of China nuclear energy. Technical solutions for the simulator of China Experimental Fast Reactor (CEFR), modeling and simulation are mainly introduced. CEFR adopted a pool-type FR technology with three-loops, which has 216 subsystems. The full...
Mrs
Martine BLAT YRIEIX
(EDF R&D MMC)
6/28/17, 1:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Stainless steels are widely used in Sodium Fast Reactor and exhibit a very satisfactory feedback regarding their behavior in contact with high purity sodium.
The French past experience with Phenix and Superphenix confirmed this trend but it also highlighted that utilities have to take care at material susceptibility to different corrosion mechanisms during maintenance operations: Stress...
Mr
Konstantin Dvoeglazov
(Institution Innovation and Technology Center by “PRORYV” Project)
6/28/17, 1:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Pyrochemical, hydrometallurgical and combined (pyro + hydro) technologies for reprocessing of mixed nitride uranium-plutonium fuel are under development in RUSSIA now. The main product of hydrometallurgical and combined processing is a mixed U, Pu and Np oxides.
The following technologies of actinides oxides preparation have been investigated for the choice of most promising: precipitation of...
Mr
Christophe Venard
(CEA)
6/28/17, 1:50 PM
Within the framework of the French ASTRID project, core design studies are being conducted by the CEA with support from AREVA and EDF. The design studies include the GEN IV reactor objectives, particularly in terms of improving safety.
Options selection was performed at the conclusion of the pre-conceptual design phase. The CFV core was confirmed as the reference core for the ASTRID...
Mr
THEODORE COZZIKA
(CEA MARCOULE)
6/28/17, 2:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
French fast breeder nuclear plant PHENIX was definitively shut down in 2009. The dismantling preparations operations of some of PHENIX components are underway. Since 2008, CEA, EDF and AREVA have identified more than twenty relevant components of PHENIX, to get the most from the feedback of the components behavior.
Feedback regarding PHENIX components materials like austenitic stainless...
Mr
Andrei Stremin
(JSC NIKIET, Moscow/Russia)
6/28/17, 2:10 PM
As part of the power unit with reactor BREST-OD-300 project justification, deterministic safety analysis with imposition of postulated single failure of systems and equipment, or human error on the initiating event (IE) was held in JSC "NIKIET". Work was done for the version of the core with jacketless TVS. The calculations were performed using the verified dynamically bound neutron-physical...
Mrs
Elena Rodina
(Innovative &Technology Center by "PRORYV" Project)
6/28/17, 2:10 PM
The article examines approaches to developing a core for a high-power lead-cooled fast reactor in compliance with the formulated safety requirements and technical and economic specifications. A particular focus is made on achieving inherent safety properties, such as: a negative void effect, negative reactor power and coolant temperature coefficients, uniform coolant heating in the reactor...
Prof.
qingsheng wu
(Institute of Nuclear Energy Safety Technology, CAS · FDS Team)
6/28/17, 2:10 PM
Abstract:
An Accelerator Driven System (ADS) project for nuclear waste transmutation has been launched by Chinese Academy of Sciences (CAS) since 2011. China LEAd-based Reactor (CLEAR) was selected as the reference reactor for the CAS ADS project and was designed and developed by Institute of Nuclear Energy Safety Technology (INEST), CAS. According to the research and development roadmap of...
Dr
Shigeru Takaya
(Japan Atomic Energy Agency)
6/28/17, 2:10 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Basic principles of maintenance management for prototype reactors are proposed in this paper. One of main missions of prototype reactors is R&D for commercializing advanced reactors, which shall be appropriately considered in maintenance management for prototype reactors. Development of maintenance programs suitable to a reactor type is one of key features of the proposed basic principles of...
Mrs
Nastasia Mosunova
(Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN))
6/28/17, 2:30 PM
The EUCLID/V1 integrated computer code is designed for the safety analysis and justification of the new generation NPPs with liquid metal cooled fast reactors under normal operating conditions, design basis accidents and beyond design basis accidents. The EUCLID/V1 code includes the system thermohydraulics module, spatial time-dependent neutronics module, quasi two-dimensional fuel rod module...
Mr
Dmitry Lukyanov
(JSC «SSC RF-IPPE»)
6/28/17, 2:30 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Sectoral monitoring tightness system of fuel elements claddings (SSKGO) is important for the reactor facility (RF) safety and designed for fuel cladding state and appearance and development of the «fuel-coolant contact» defects operational control. Developers of the system are: JSC «IPPE» and JSC «Afrikantov OKBM».
Modernized SSKGO system (3N safety class) of RF BN-600 and SSKGO system (3NU...
Dr
NATHALIE REYNIER TRONCHE
(CEA, Nuclear Energy Division, RadioChemistry and Processes Department), Ms
emilie buravand
(CEA MARCOULE)
6/28/17, 2:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
In the scope of fast reactor spent fuel recycling, head-end research and development are performed at the Atalante facility in Marcoule. Considering the initial plutonium content, quantitative plutonium recovery is one of the main objectives for the dissolution process. In addition, the quantities of undissolved residue increase with the burn up and can impact the waste conditioning...
Mr
Aleksey Bochkarev
(NRC "Kurchatov Institute")
6/28/17, 2:30 PM
This study presents the inherent safety performance of BN-type reactor 2800 MW of thermal power with MOX core during ATWS initiated by various accident initiating events with simultaneous failure of all shutdown systems in all cases under investigation.
The most severe cases leading to the pin cladding rupture and possible sodium boiling were found out.
The impact of various safety features...
Mr
Sergey Belov
(JSC “Afrikantov OKBM”)
6/28/17, 2:30 PM
The core of a commercial reactor BN-1200 designed for operation with developed MOX-fuel or advanced nitride fuel. The common approach to the design of the specified cores was:
- reduction of the fuel rating, in comparison with BN-600 and BN-800, which permits to use larger fuel pins (Ø 9.3 mm) to reduce their consumption and minimizing reactivity margin for fuel burn-up;
- use of the fuel...
Ms
Marianne GIRARD
(Commissariat à L'Energie Atomique et aux Energies Alternatives)
6/28/17, 2:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
An electrochemical hydrogen meter (ECHM) developed in IGCAR, India has been tested in a sodium facility in CEA Cadarache, France as part of IGCAR-CEA collaboration of fast reactor safety. ECHM is basically a concentration cell which can be used for online monitoring of hydrogen concentration in ppb levels in liquid sodium in order to detect the eventuality of steam leak in the sodium circuit...
Mr
Venkatesan Arasappan
(Indira Gandhi Centre for Atomic Research)
6/28/17, 2:50 PM
Track 2. Fast Reactor Operation and Decommissioning
ORAL
Abstract: The purposes of Instrumentation and Control systems are to assist the operator in controlling the plant at the specified power level, monitor the plant and warn of deviations from normal conditions, prevent accidents by carrying out independent automatic safety and control actions, and mitigate consequences of an accident automatically. Design of I&C for PFBR is done in...
Mr
Eugeny Varseev
(ROSATOM-CICE&T)
6/28/17, 2:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Provision of the safe and reliable operation of Nuclear Power Plant with sodium fast reactor requires maintaining of the quality of the sodium coolant in regards of oxygen and hydrogen contents at the specific level, since even a few parts per million of sodium oxide can have a deleterious effect on the performance and reliability of a fast reactor cooled by sodium and its heat transfer...
Mr
Christophe Venard
(CEA)
6/28/17, 2:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Amid the ASTRID’s main goals, one of them is to demonstrate the full fuel cycle closing at the industrial scale. In particular with the recycling of plutonium coming from the treatment of UOX and MOX fuels from PWRs and also the MOX coming from ASTRID itself. Associated with the fuel cycle facilities, fabrication and reprocessing, the lessons learned from this industrial demonstration will be...
Eirik Eide Pettersen
(Paul Scherrer Institut)
6/28/17, 2:50 PM
Fast reactors that circulate liquid fuel exhibit a strong coupling between neutronics and thermal-hydraulics that necessitates the use of coupled multi-physics codes to study dynamic behaviour. Presently, most such tools employ computational fluid dynamics (CFD) to resolve thermal-hydraulics. This paper concerns an alternative approach in which the system code TRACE is used to compute...
315.
ADVANCED FLOW-SHEET FOR PARTITIONING OF TRIVALENT ACTINIDES FROM FAST REACTOR HIGH ACTIVE WASTE
Mr
Balija Sreenivasulu
(IGCAR)
6/28/17, 3:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Partitioning of radiotoxic elements present in the high-level liquid waste (HLLW) followed by transmutation of them (P&T strategy) into stable or short-lived products in accelerated driven systems or fast-reactors is a viable option for the safe management and minimizing the radiotoxicity of HLLW. In this context, a typical high-active waste (HAW) arising from reprocessing of spent carbide...
Prof.
Akira Yamaguchi
(The University of Tokyo)
6/28/17, 3:30 PM
The safety design criteria (SDC) has been established in the framework of the Generation-IV International Forum by incorporating safety-related R&D results on innovative technologies and lessons-learned from Fukushima Dai-ichi nuclear power plants accident in order to provide the set of general criteria for the safety designs of structures, systems and components of Generation-IV sodium-cooled...
Mr
Aleksandr Sorokin
(SSC RF - IPPE),
Julia Kuzina
(SSC RF - IPPE)
6/28/17, 3:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In the report heat transfer and temperature non-uniformities over the perimeter of the pins in the free-packed pin bundles (s/d=1,33, s/d=1,28) with heavy liquid-metal coolant are considered at various spacing ways. Experimental data for three pin bundles are analyzed: a bundle of smooth fuel pins, a bundle of fuel pins spaced by bilifar-helix wire wrapper of «wire to wire» type and a bundle...
Mr
Aleksandr Legkikh
(JSC “SSC RF – IPPE”)
6/28/17, 3:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Heavy liquid metal coolants (HLMC) including lead-bismuth and lead make significant corrosion and erosion impact on structural steels. The only way to assure the long-term reliable operation of steels of the primary system components operating in contact with HLMC is to provide protective coating on the steel surface. By now, oxygen-based technology of structural steel surface passivation has...
Dr
Michele Frignani
(Ansaldo Nucleare S.p.A.)
6/28/17, 3:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
Fast reactors, selected at European level as next generation Nuclear Energy Systems, pose undeniable challenges from a technological point of view. In order to support the foreseen deployment strategy, a survey of the existing industrial supply chain have been thoroughly carried out in terms of its capabilities and potentialities with respect to Fast Reactors needs.
The main challenges found...
Dr
Toshinobu Sasa
(Japan Atomic Energy Agency)
6/28/17, 3:30 PM
The management of radioactive waste is one of the critical issues for sustainable nuclear energy application especially after the Fukushima accident. In the latest strategic energy policy of Japan express to enhance a research and development to reduce the burden of long-lived nuclides in spent nuclear fuel using both fast reactors and accelerator-driven systems (ADS). Japan Atomic Energy...
Mr
Laurent VOLPE
(French Atomic Energy Commission)
6/28/17, 3:50 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
CEA is the contracting authority and industrial architect of ASTRID Project, an industrial prototype of 4th generation Sodium Fast Reactor. This reactor of 600 eMW is integrating French and international SFRs feedback, especially in domains of safety, operability and ultimate wastes transmutation. The project is funded for basic design phase (2016-2019) through France Future Investments...
Mr
CLEMENT RAVI CHANDAR SOWRINATHAN
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
6/28/17, 3:50 PM
To provide rapid growth and faster deployment of fast breeder reactors in future,
metal fuelled reactors are planned. The Design safety limits (DSL) for normal and anticipated
transient events are arrived at for a typical 500 MWe metal fuelled reactor, which is
addressed in this paper.
All the design basis events occurring during the lifetime of the components concerned
are classified...
Dr
Concetta Fazio
(JRC)
6/28/17, 3:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The design objectives of Fast Reactors (FR) are mostly related to safety, sustainability and economics; waste minimisation is also considered. To meet these objectives, the selection of structural and fuel clad materials is a crucial issue to be considered. Indeed, the materials in FR environment can be subject to intense mechanical stresses, a high energetic neutron field and circulating heat...
Prof.
Alexei Potapov
(Institute of High Temperature Electrochemistry)
6/28/17, 3:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
The scientific and technological aspects of the pyrochemical recycling of uranium-plutonium nitride nuclear fuel used in the circuited nuclear fuel cycle on the basis of nuclear power plant with fast neutron reactors were considered (in the framework of "Breakthrough" Project). It was expected that the developed pyrochemical technology allows recycling spent nuclear fuel with high energy...
Mr
Rafael Fernandez
(Belgian Nuclear Research Centre (SCK.CEN))
6/28/17, 3:50 PM
MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a multipurpose research facility being developed since 1998 at SCK•CEN, based on the Accelerator Driven System (ADS) concept where a proton accelerator, a spallation target and a lead-bismuth cooled subcritical reactor are coupled. MYRRHA will demonstrate the ADS full concept by coupling these three components at a...
Dr
Julio Pacio
(Karlsruhe Institute of Technology)
6/28/17, 3:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The development of the LBE-cooled MYRRHA fuel assemblies is supported by an extensive thermal-hydraulic experimental program, as well as numerical studies. For the safety assessment of the reactor, several experimental campaigns considering fuel assembly mockups in representative operating conditions have been completed, and others are ongoing and planned at KIT (Germany) and SCK•CEN...
Dr
Liudmila Tkachenko
(Khlopin Radium Institute)
6/28/17, 4:10 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
The fast reactors and related fuel cycle technologies are extensively development at present. It is possible to transmutate the radiotoxic nuclides, contained in PUREX raffinates (primarily minor actinides), in fast reactors. This raises the challenge of minor actinides recovery from PUREX raffi-nats.
The process for actinides (III) partition with solvent based on...
Mr
Andrey Balanin
(NRC "KurchatovI Institute")
6/28/17, 4:10 PM
At the turn of the century a new step in the development of gas cooled fast reactors (GCFR) in the world was made through international cooperation in the elaboration of innovative nuclear energy systems. In the mid of 2000s, in Russia rather active investigations in this direction were resumed under the scientific supervision of NRC "Kurchatov Institute", what happened largely due to the...
Dr
Nikita Rtishchev
(IBRAE RAN), Mr
Ruslan Chalyy
(IBRAE RAN)
6/28/17, 4:10 PM
The SOCRAT-BN integral code has been developed in frame of Federal Target Program «New-Generation Nuclear Power Technologies for the Period 2010–2015 and up to 2020». The code is intended for safety justification of NPPs with sodium-cooled reactors under DBA and BDBA including those that lead to core melting.
The modules integrated into SOCRAT-BN code allow to perform coupled simulation of...
Dr
Alexander Aerts
(Belgian Nuclear Research Centre)
6/28/17, 4:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In 2010 the Chemistry and Conditioning Programme (CCP) was established to provide R&D support for the engineering and licensing of the MYRRHA nuclear system under development at the Belgian Nuclear Research Centre (SCK-CEN). MYRRHA is an accelerator-driven subcritical nuclear reactor with fast neutron spectrum, using liquid lead-bismuth eutectic (LBE) as spallation target material and coolant....
Dr
Michele Frignani
(Ansaldo Nucleare S.p.A.)
6/28/17, 4:30 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
In the European context, the implementation of the Generation-IV vision for safer, more sustainable, economic and proliferation resistant nuclear energy systems is being pursued as long-term action of the EU's strategies for a sustainable scenario securing energy availability. This action, envisaging innovative reactor concepts to implement the Gen-IV vision, is supported by the European...
Mr
Máté Gergely Halász
(Budapest University of Technology and Economics, Institute of Nuclear Techniques)
6/28/17, 4:30 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Due to the high computational cost of detailed burn-up calculations, most scenario codes use burn-up tables or parametrized few group cross-sections to calculate fuel depletion in reactors. As a special parametrization approach, a fast and flexible burn-up scheme called FITXS was developed at the BME Institute of Nuclear Techniques, which is based on the fitting of one-group cross-sections as...
Ms
Morena Angelucci
(University of Pisa)
6/28/17, 4:30 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The NACIE-UP facility at ENEA-Brasimone R.C. is a large scale loop operating with Lead Bismuth Eutectic (LBE) in the range of 180°C-450°C in free and mixed convection. The difference in height between heat source and heat sink is about 4.5 m and allows the establishment of natural circulation regime inside the loop. Moreover, a gas-lift system provides the pressure head to enhance the...
Mr
Radomir Askhadullin
(JSC “SSC RF – IPPE”)
6/28/17, 4:30 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Up to date, the following three main problems can be emphasized concerning technology of Pb-Bi and Pb coolants used in the civilian reactors:
1) maintaining high purity of coolant and cleanness of the surfaces of NPP circuits in order to assure design thermal-hydraulic performance of the plant operating on power up to 100 % during several decades;
2) long-term prevention of corrosion and...
Dr
Staffan Qvist
(LeadCold AB)
6/28/17, 4:50 PM
The Autonomous Reactivity Control (ARC) system was developed to ensure inherent safety of fast reactors while having a minimal impact on reactor performance and economic viability. The ARC system is a modification to a standard fast reactor fuel assembly, in which two liquid-filled reservoirs, one above and one below the core, are connected by a tube which replaces one of the fuel rods in the...
Ms
Delphine GERARDIN
(FRANCE / LPSC-IN2P3-CNRS - Université Grenoble Alpes)
6/28/17, 4:50 PM
The CNRS has focused R&D efforts on the development of a new reactor concept called the Molten Salt Fast Reactor (MSFR). The MSFR, characterized by a circulating liquid fuel and a fast neutron spectrum, has been identified as a very interesting long term alternative to solid fuelled fast neutron systems in the Gen4 International Forum.
MSRs are liquid-fuelled reactors so that they are...
Dr
Kirill Shutko
(N.A. Dollezhal Research and Development Institute of Power Engineering)
6/28/17, 4:50 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The compatibility of water chemistry with structural materials of steam-water cycle is most important condition for long-term operational reliability of steam generators. Limiting service life factor of the steam generators is usually corrosion damages of heat exchanger tubes from the steam-water side. In view of this the mostly proven in practice reference design and engineering solutions...
Mr
Nico Krauter
(Helmholtz-Zentrum Dresden - Rossendorf)
6/28/17, 4:50 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
For the safe operation of sodium cooling systems a monitoring of the flow field is often desirable. We report first on the development of a new eddy current flowmeter (ECFM) and related tests in sodium. The objective of this sensor is its positioning above the fuel subassemblies and the detection of possible blockages of the sodium flow through the multitude of subassemblies. The sensor...
Andrei Shadrin
(Bochvar Institute), Dr
Vitaliy Vidanov
(INSTITUTION «ITC «PRORYV» PROJECT»)
6/28/17, 4:50 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Modern technology for reprocessing of spent nuclear fuel (SNF), corresponding to a closed fuel cycle concept is developed in the framework of the «PRORYV» PROJECT». This technology require separation of Am from Cm and REE. Americium can be transmutated in fast reactors.
Two-stage technology of Cm and Am separation from REE-TPE concentrate was tested on Mayak Production Association. Used...
Dr
Alexander CHEBESKOV
(IPPE)
6/28/17, 4:50 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
Methodologies have been developed within the Generation IV International Forum (GIF) to support the assessment and improvement of system performance in the areas of sustainability, safety and reliability, economics, proliferation resistance and physical protection (PR&PP). The last of these four areas was assigned to the GIF Working Group on Proliferation Resistance and Physical Protection...
Mr
Oleg Saraev
(Russian Federation State Atomic Energy Corporation "Rosatom")
6/28/17, 5:10 PM
Track 7. Fast Reactors and Fuel Cycles: Economics, Deployment and Proliferation Issues
ORAL
The modern open fuel cycle nuclear power has created a number of obstacles for its further development due to enormously low effectiveness of natural uranium use, accumulation of nuclear wastes in thermal reactors, its increasing environmental unacceptability, limited explored natural uranium stockpiles and instability of natural uranium market price originated from the reasons similar to...
Dr
Edwin Lyman
(Union of Concerned Scientists)
6/28/17, 5:10 PM
Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues
ORAL
Some advocates of electrometallurgical reprocessing (or “pyroprocessing”) of spent nuclear fuel argue that the technology has many advantages relative to aqueous reprocessing methods, including cost savings, safety benefits, and increased proliferation resistance. However, to date there has been very little actual operating experience with production-scale electrometallurgical processes,...
Dr
Ladislav Bělovský
(ÚJV Řež, a. s.)
6/28/17, 5:10 PM
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
ALLEGRO is a helium-cooled experimental fast reactor, which is under development by the consortium „V4G4 Centre of Excellence” (Czech Republic, Hungary, Poland and Slovakia) associated with France. The current pre-conceptual stage of development by the V4G4 CoE is based on the 75 MWt concept presented by CEA in 2009. The main purpose of ALLEGRO is 1) Demonstration of viability of the...
Dr
Štefan Čerba
(Slovak University of Technology in Bratislava)
6/28/17, 5:50 PM
Slovakia is involved in the development of the ALLEGRO reactor, the demonstrator of the unique GFR technology. Since the Gas-cooled Fast Reactor lacks any applicable experimental data, the design and optimization of its core must rely on data from similar reactor concepts and on calculations using Monte Carlo and deterministic methods. Although these two methods differ in their nature, both...
Mr
JEAN-MARIE HAMY
(AREVA NP)
6/28/17, 5:50 PM
The purpose of this paper is to describe in a first part a coupling methodology between two codes in order to describe global thermalhydraulic behavior inside a sodium-cooled fast reactor. A CFD code (STAR-CCM+) is used for the modelling of primary circuit, while a system code (CATHARE) is used for the modeling of specifics area in primary circuit (core structures and primary pumps) and the...
Mr
Bálint Batki
(Centre for Energy Research, Hungarian Academy of Sciences)
6/28/17, 5:50 PM
In this study, the fuel, the coolant, the cladding and the wrapper temperature reactivity coefficients were calculated with Serpent Monte Carlo code for the ALLEGRO demonstrational GFR core and for an SFR core with 3600 MWth power. The results were compared with each other and with thermal reactor reactivity coefficients, and it was found that the thermal expansion of the core structural...
Mr
Xiaoliang Chen
(China Institute of Atomic Energy)
6/28/17, 5:50 PM
China Experimental Fast Reactor (CEFR) has completed physics start-up tests in 2010 and connected the grid on FP in 2014. Characteristic of neutron field for irradiation in CEFR has been researched by calculation and experiments. In future, CEFR will been operated as an irradiation test facility for fuel, material and other application, and some irradiation projects, such as irradiation of...
Dr
Willem Frederik Geert Van Rooijen
(Research Institute of Nuclear Engineering, University of Fukui)
6/28/17, 5:50 PM
A Coordinated Research Project (CRP), initiated by the International Atomic Energy Agency (IAEA), consisted of benchmark calculations with the goal to analyze two of the Shutdown Heat Removal Tests performed in EBR-II, namely SHRT-17 and SHRT-45R. Test SHRT-45R concerned an Unprotected Loss Of Flow (UOLF) scenario. In this case, only the inherent feedback mechanisms due to the change of the...
Mrs
Irina Chernova
(Nuclear Safety Institute of Russian Academy of Sciences)
6/28/17, 5:50 PM
A module of transient neutron transport problem solution is an essential part of complex codes designed for the analysis of nuclear safety in different modes of operation of a nuclear reactor. The neutron transport problem can be solved with a variety of approximate schemes, such as point kinetics, adiabatic, quasi-static and improved quasi-static approximations or direct numerical solution of...
Mr
Alexey Tutukin
(Vladimirovich)
6/28/17, 5:50 PM
Information has been obtained on the flow distribution along parallel paths, on the
situation of the free levels, on the heat and mass transfer processes. Experimental
determination of the hydraulic parameters is only possible for the components of the core by
using full-scale mock-ups. The remaining elements of the circulation loop require calculation
justification supported by...
Dr
Tai Asayama
(Japan Atomic Energy Agency)
6/28/17, 5:50 PM
Grade 91 steel is a Code-approved construction material in the ASME and JSME nuclear codes. Applications of Grade 91 steel include intermediate heat exchanger, piping, steam generator tubing and shell, etc. for sodium fast reactor systems. Current creep-fatigue damage evaluation method in the ASME and JSME nuclear code differs in the method to calculate creep damage. In the simplified...
Dr
Hidemasa Yamano
(Japan Atomic Energy Agency)
6/28/17, 5:50 PM
This paper describes basic visualization experiments on eutectic reaction and relocation of boron carbide (B4C) and stainless steel (SS) under a high temperature condition exceeding 1500°C as well as the importance of such behaviors in molten core during a core disruptive accident in a Generation-IV sodium-cooled fast reactor (750MWe class) designed in Japan. At first, a reactivity history was...
Dr
Chiwoong CHOI
(Korea Atomic Energy Research Institute (KAERI))
6/28/17, 5:50 PM
KAERI has joined the International Atomic Energy Agency (IAEA) coordinated research project (CRP) on Benchmark Analysis of an EBR-II Shutdown Heat Removal Test (SHRT). The major goal for this program is to validate MARS-LMR, which is a newly developed safety analysis code for PGSFR. One of benchmark tests is a SHRT-45R, which is an unprotected loss of flow test in an EBR-II. Thus, sodium...
Mr
Moustafa Aziz Ibrahim
(Nuclear and Radiological Regulatory authority)
6/28/17, 5:50 PM
The BN-600 reactor is a sodium-cooled fast breeder reactor, built at Russia. Designed to generate electrical power of 600 MW in total. IAEA has considered the reactor for many phases of benchmark problems.The coordinated research project activities were started in 1999 and included studies fora so-called hybrid BN-600-reactor-type core model, partially fuelled with highly enriched uranium and...
Mr
Yury Naboyshchikov
(JSC "State Scientific Center - Research Institute of Atomic Reactors")
6/28/17, 5:50 PM
At present, a wide range of tests is performed in the BOR-60 reactor in support of reactors under operation, construction and design in Russia and worldwide. Most of the tests are performed in the reactor core regions of the peak dose accumulation rates. However, there is a high demand for irradiation testing to be performed in the BOR-60 blanket.
An important feature of any nuclear...
Mr
Artem Varivtcev
(JSC “SSC RIAR”)
6/28/17, 5:50 PM
At present, different nuclear fuels (NF) to be used in advanced fast neutron reactors (AFR) are tested in the BOR-60 reactor. In such in-pile testing the top priority is to ensure the maximum possible compliance of the target NF irradiation parameters with the design operating parameters. The key monitored parameters in testing experimental fuel elements are the fuel burnup rate and linear...
Mr
Yonghoon Shin
(Seoul National University)
6/28/17, 5:50 PM
We present results of experiments with lead-bismuth eutectic (LBE) non-isothermal natural circulation in a full-height scale test loop, HELIOS, and numerical modeling results performed by a system thermal-hydraulics code. The experimental studies were conducted under steady state as a function of core power conditions from 9.8kW to 33.6kW. Local surface heaters on the main loop were activated...
Prof.
Nikolay Maksimov
(National research nuclear university (Moscow Engineering Physics Institute))
6/28/17, 5:50 PM
The results of the analysis of terminological subsets of the characteristic lexicon, that is used for semantic identification of scientific and technical information in the field of fast neutron reactors is discussed. Describes the procedure of automatic formation of ordered dictionaries reference lexicon based on the full text processing of documents – scientific reports, dissertations,...
Ms
Xiuli Xue
(Senior engineer)
6/28/17, 5:50 PM
For the lacking of applicable code to analyze emergency heat removal capacity of pool-style fast reactors, it is developed according to the design requirement of demonstration fast reactors. The code builds a consolidated platform developing modules of reactor core, sodium pool, relevant components and so on individually from one-dimension to three-dimension, forming program module packages...
Mr
Victor Blandinskiy
(NRC "Kurchatov Institute")
6/28/17, 5:50 PM
Multifunctional fast neutron research reactor MBIR is intended to provide the basis for broad scope of research and experimental activities due to achieving 5E15 n/cm2/s integral neutron flux in central loop channel, i.e. MBIR is considered as neutron source of high intensity.
This work focuses on the possibilities of the use of different fuel in MBIR to provide required neutron flux in loop...
Mr
David Wootan
(Pacific Northwest National Laboratory)
6/28/17, 5:50 PM
The FFTF was designed to accommodate up to four CLS. Each CLS was an irradiation testing system capable of operating at 2.3 MWt with its own independently controlled coolant system. An irradiation test in a CLS was inserted into the core within a Closed Loop In-Reactor Assembly (CLIRA). An entire CLS consisted of a CLIRA, a primary and a secondary cooling loop, and a Dump Heat Exchanger...
Mr
Puthiyavinayagam Pillai
(Indira Gandhi Centre for Atomic Research)
6/28/17, 5:50 PM
In the case of Indian Prototype Fast Breeder Reactor (PFBR), which is in an advanced stage of commissioning, the fuel pins along with other parts of fuel subassembly are stored in an Interim Fuel Storage Building (IFSB). The final assembling of subassembly is carried out in IFSB and the IFSB is located far away from PFBR site. It is essential to demonstrate safe transportation of the fuel...
Dr
Romain Coulon
(CEA LIST)
6/28/17, 5:50 PM
The cleanliness of the primary circuit is a safety requirement for Generation IV nuclear power plants. During operation, fission product concentration into the sodium coolant has to be monitored by dedicated radiation monitoring systems. These systems are based on neutron counting and gamma spectroscopy. Neutron detection allows detecting clad failure when its opening is large enough to...
Prof.
liqin hu
(Institute of Nuclear Energy Safety Technology, CAS · FDS Team)
6/28/17, 5:50 PM
Abstract:
Compared with the other reactor types, the neutron spectrum of fast reactors is hard, affecting the neutronics and safety performance, for which advanced nuclear simulation methods such as Monte Carlo method is necessary for the nuclear design. Super Monte Carlo Simulation Program for Nuclear and Radiation Process (SuperMC) is a general, intelligent, accurate and precise program...
Mr
Partha Sarathy UPPALA
(IGCAR, INDIA)
6/28/17, 5:50 PM
Experimental Breeder Reactor (EBR-II) was a U-Pu-Zr metal-alloy fueled liquid-metal-cooled fast reactor, extensively used for conducting safety experiments. Out of several tests conducted, the SHRT-17 loss of flow test conducted in 1984 demonstrated the decay heat removal capability by natural circulation in sodium cooled fast reactor with no core damage. In order to utilize the data recorded...
Mr
Nikolay Loginov
(SSC RF-IPPE)
6/28/17, 5:50 PM
Development experience for experimental reactor facility cooled with evaporating liquid metals
Loginov N.I.
State Scientific Center of the Russian Federation – Institute of Physics and Power Engineering. Obninsk, Russia
SSC RF-IPPE developed technical project of experimental reactor facility cooled with evaporating liquid metals at 1988-97. Evaporating sodium used as a coolant of the core...
Ms
Marianne GIRARD
(CEA/FRANCE)
6/28/17, 5:50 PM
Within the ASTRID reactor project, CEA, EDF and AREVA, have launched a R&D program focused on the low leak rates detection of sodium on pipes. This program is focused on the development of innovating detectors, multilayer-type and Optic Fiber, involving tests in the FUTUNA-2 sodium loop. This loop is designed to produce very accurate sodium leak rates within a range around 1 cc/min, the tests...
Mr
Alexander Tuzov
(JSC "SSC RIAR")
6/28/17, 5:50 PM
This paper presents the technical parameters and the experimental capabilities of the MBIR reactor; it shows the main reactor engineering solutions of the project and describes the key events related to the implementation of the MBIR construction project.
Mr
Tanju Sofu
(Argonne National Laboratory)
6/28/17, 5:50 PM
Inherent and passive safety is a key aspect to achieve licensing assurance and reduce plant costs, but it requires demonstration and validation of key features. To address this need, DOE-NE's Advanced Reactor Technologies (ART) program supported development of EBR-II, FFTF, and TREAT safety testing databases, metal fuel irradiation database, EBR-II physics analysis database and materials...
Dr
Tyler Sumner
(Argonne National Laboratory)
6/28/17, 5:50 PM
In 2012, the International Atomic Energy Agency (IAEA) established a coordinated research project (CRP) on EBR-II Shutdown Heat Removal Tests (SHRT). The objectives of the CRP, which concluded in 2016, were to improve design and simulation capabilities in fast reactor neutronics, thermal hydraulics, plant dynamics, and safety analyses through benchmark analysis of two landmark tests performed...