Mr
Aleksei Sedov
(NRC "Kurchatov Institute")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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”)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
“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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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))
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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...
Mr
David Lemasson
(EDF)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
The validation of severe accident analysis codes for Sodium Fast Reactors (SFR) is a difficult task as it is not possible to carry out full scale integral experiments. Therefore, in addition to the validation of specific models with dedicated experiments, it is of the utmost importance to increase the confidence we have in these codes by performing benchmarking exercises with independent codes...
Christopher Matthews
(Los Alamos National Laboratory)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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))
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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»)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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»)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
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...
Iurii Ashurko
(IPPE)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
Decay heat removal system (DHRS) option for the secondary circuit of the sodium-cooled fast reactor (SFR) by means of air cooling the outer surface of piping and equipment of heat removal loops of the SFR secondary circuit is proposed.
The DHRS option under consideration implies case mounted around main piping and equipment of heat removal loops of the SFR secondary circuit and divided into a...
Mr
IURII SHVETSOV
(Private institution «Innovation and technology center for the «PRORYV» project»)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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»)
27/06/2017, 17:30
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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...
Dr
FABIEN ROUILLARD
(CEA)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
The need for materials having good tribological properties in Sodium Fast Reactors has been identified (SFR) from the first reactors operation. Where galling or adhesive wear cannot be tolerated, hardfacing alloys or galling-resistant coatings are usually applied on rubbing surfaces. The most used coating is the cobalt base alloy named Stellite because of its outstanding friction and wear...
Mr
Yoshihiro Sekio
(Japan Atomic Energy Agency)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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»)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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
Bangyue YIN
(CIAE)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
In order to increase dissolution ratio of the irradiated NpO2 targets, it’s necessary to add a little diluent into NpO2 pellet. In this paper, pressureless sintering processes and microstructures of NpO2-10% CaO, NpO2-10%SrO, NpO2-10%MgO and NpO2-5%MgO pellets were studied, sintered at 1730℃ for 2 hours in Ar-5%H2 gases. Only NpO2 solid solution phase structure was found in all the pellets....
Mr
Balija Sreenivasulu
(IGCAR)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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.)
27/06/2017, 17:30
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)
27/06/2017, 17:30
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»)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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))
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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...
Mr
Denis Lorenzo
(CEA)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
This paper reports on preliminary studies performed regarding the insertion reliability of the RBC-type Control Rods designed for the ASTRID Sodium-cooled Fast Reactor. At this stage, the primary aim of the analysis is to evaluate the mechanical behaviour of RBC Control Rods under Emergency Shutdown conditions, for which reactor core structures are subjected to significant misalignments...
Irina Portnykh
(Joint Stock Company "Institute of Nuclear Materials")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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))
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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))
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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...
Dr
Cetin Unal
(LANL)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
C. Unal1, X. Li2, J. Isler2, S. Abid2, J. Zhang2, C. Matthews1, C. Arnold4, J. Galloway1, N. Carlson1, R. Mariani3
1 Los Alamos National Laboratory
2Ohio State University
3Idaho National Laboratory
4Pajarito Scientific Corporation
fission products as well as lanthanide impurities in recycled feedstock are known to migrate to the periphery of metal fuels and initiate FCCI that...
Ms
Inga Makeyeva
(RFNC-VNIITF)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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”)
27/06/2017, 17:30
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
Benjamin Hary
(CEA)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
Oxide dispersion strengthened (ODS) ferritic steels are promising candidates for high burn up fuel pins of Sodium Fast Reactors. They are elaborated by powder metallurgy and their manufacturing route is complex and specific, including hot forming and cold working. Different heat treatments are necessary to recrystallize these materials and to relieve internal stresses. The presence of highly...
Mr
Jean-Baptiste GENIN
(CEA, DEN)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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...
Mr
Edouard Bissen
(CEA)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
Sodium-cooled Fast Reactors (SFR) is one of the Generation IV reactor concepts. It has been selected to secure the nuclear fuel resources and to manage radioactive waste. In this context, the CEA (French Commission for Atomic Energy and Alternative Energy) with its partners is involved in a substantial effort on the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration)...
Dr
Staffan Qvist
(LeadCold AB)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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...
Ms
Sara Bortot
(KTH)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
Within the European FP-7 project PELGRIMM, oxide fuel forms for Minor Actinide (MA) transmutation were researched for both homogeneous and heterogeneous recycling in Sodium-cooled Fast Reactors (SFRs).
Among the investigated fuels, sphere-pac fuels were given priority emphasis, as they offer great advantages compared to pellet fuels when MAs are to be embedded, while presenting, however,...
Mr
Ignas Mickus
(LeadCold Reactors)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
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
Didier Costes
(CEA)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
The resting bottom sodium vessel may receive several applications. For a fast reactor, the direct gas circuit without intermediary sodium may increase the thermal efficiency and, conveniently studied, presents no risk of gas arrival perturbing the core. A construction economy seems to appear and, at end of use, the under soil vessel needs no dismantling and could contain radioactive remains,...
Mr
Dmitry Blagodatskykh
(Nuclear Safety Institute (IBRAE RAN))
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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”)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
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”)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
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...
Yurij Osheyko
(none)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
Well-known vulnerability points for sodium-cooled reactors are:
– chemical interaction of sodium and water;
– three-circuits reactor design;
– increased material consumption and building cost compared to PWR and BWR;
– increased on-site amount of building and assembling operations.
The most of these difficulties can be solved with replacing steam turbine by specially designed gas...
Dr
Giacomo Grasso
(Italian National Agency for New Technology, Energy and Sustainable Economic Development (ENEA))
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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...
Mr
Jeonghyeon Lee
(UNIST)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
Ferritic-martensitic steel (FMS), which contains 9-12 wt.% of chromium, is being considered as an attractive candidate material for a fuel cladding of a sodium-cooled fast reactor (SFR) due to their high thermal conductivities, low expansion coefficients and excellent irradiation resistances to a void swelling compared with austenitic stainless steels [1, 2]. The cladding should have excellent...
Dr
Kyoichi Morimoto
(Japan Atomic Energy Agency)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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")
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
Track 1. Innovative Fast Reactor Designs
POSTER
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")
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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")
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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)
27/06/2017, 17:30
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
Pietro Agostini
(ENEA)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
The development of Pb and LBE cooled fast reactors represents a unique challenge for the materials that are subject, at the same time, to degradation mechanisms related to neutron radiation damage, exposure to high temperatures and exposure to the HLM. The protection towards HLM corrosion, in the past, has been based on the control of the oxygen concentration in the HLM by keeping the oxygen...
Dr
Nicolas Stauff
(Argonne National Laboratory)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
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)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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)
27/06/2017, 17:30
Track 3. Fast Reactor Safety
POSTER
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”)
27/06/2017, 17:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
POSTER
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...
