Dr
Kyriakos Christodoulides
(Createc)
POSTER
A realistic and reliable monitoring of Highly Active (HA) wastes and infrastructure is one of the most important challenges currently facing the nuclear industry. Despite the constraints and potential dangers imposed by high intensity radiation, there exists an increasing necessity to monitor HA environments in nuclear reprocessing and decommissioning. Gamma imaging has already been proven to...
Mr
John Scaglione
(Oak Ridge National Laboratory)
ORAL
A fully integrated waste management system involves managing the waste from the time it is discharged from the reactor and designated as spent nuclear fuel (SNF) to the time it is disposed of in a geologic repository. Performing the different types of analyses required to account for the changing nuclear and mechanical characteristics of SNF over time, and understanding how these...
Marissa Bailey
(U.S. Nuclear Regulatory Commission)
ORAL
The OECD Nuclear Energy Agency (NEA) assists member countries in ensuring the adequate safety of existing and future nuclear installations, through maintaining and developing the knowledge, competence and infrastructure needed to regulate and support the complete life cycle. NEA’s Working Group on Fuel Cycle Safety (WGFCS) brings together representatives of regulatory bodies, their technical...
Dr
Raul Versaci
(Comision Nacional de Energia Atomica)
POSTER
Argentina has three nuclear Power Plants in operation, Atucha I (CNA I), Embalse (CNE) and Atucha II (CNA II). All of them are based on natural uranium as fuel with heavy water moderation and refrigeration.
Atucha I (370 Mwe) and Atucha II (750 Mwe) are almost unique in their type, both are Pressure Vessel type. The Embalse Nuclear Power Plant ( 600 Mwe) is a CANDU type.
In this work we...
Dr
Bernhard Droste
(BAM Federal Institute for Materials Research and Testing)
ORAL
Abstract: When storage of spent nuclear fuel (SNF) is done in dual purpose casks (DPC), the effects of aging on safety relevant DPC functions and properties have to be managed in a way that a safe transport after the storage period of several decades is capable, and can be justified and certified permanently throughout that period. The effects of aging mechanisms (like e.g. radiation,...
Dr
Barbara Charlotte Oberländer
(Institutt for Energiteknikk, OECD Halden Reactor Project), Ms
Vendi Andersson
(Institutt for energiteknikk, Kjeller, Norway)
POSTER
Spent, legacy fuel elements from the early 50s and 60s originating from the first Norwegian RR, JEEP I, are stored in an underground dry storage since the mid 60s. It is known that some of the Al-clad naturally enriched metallic uranium fuel elements had defects by the time they were discharged from the JEEP I RR and put into the cooling pond. In the mid 60s an underground dry storage site...
Mr
Ken Sorenson
(Sandia National Laboratories)
ORAL
The United States Department of Energy (DOE), Office of Nuclear Energy (NE) initiated a program in 2009 to develop the technical basis to support the licensing for long term storage and subsequent transportation of high burnup spent fuel. An initial focus of this program was development of a technical data gap analysis that identified the data gaps that needed to be addressed to support...
Dr
Konrad Linnemann
(BAM Federal Institute for Materials Research and Testing)
ORAL
Transport packages for spent nuclear fuel have to be assessed with respect to specific transport conditions which are defined in the safety regulations of the International Atomic Energy Agency. In general, gastight fuel rods constitute the first barrier of the containment system. The physical state of the spent fuel and the fuel rod cladding as well as the geometric configuration of the fuel...
Dr
Surik Bznuni
(Nuclear and Radiation Safety Center, Armenia)
POSTER
Currently two main approaches are applied to demonstrate criticality safety of spent fuel in the Back-End of the Fuel Cycle: fresh fuel approach and burnup credit approach. In the fresh fuel approach, spent nuclear fuel has a pre-known precise nuclide composition that enables to develop bounding approach to the criticality safety analysis in the Back-End of the Fuel Cycle. This approach...
Mr
Antonio Carlos Rodrigues
(IPEN-CNEN/SP)
POSTER
The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks to the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating circumstances, the storage will have capacity for approximately six years. Whereas the estimated useful life of the IEA-R1 is around twenty years, it will be necessary to...
Dr
Johan Andersson
(Swedish Nuclear Fuel and Waste Management Co. (SKB))
ORAL
The programmes for final disposal of spent nuclear fuel are similar in Sweden and Finland, and there has been extensive cooperation between the waste management organisations in the two countries over the years. Since both programmes now enter a stage of final design and implementation this cooperation will be deepened, aiming when possible for the same technical design.
The repositories in...
Mr
ZHANSHUN QI
(CHINA NATIONAL NUCLEAR CORPORATION)
ORAL
China has draw up a great nuclear power programme to satisfy the clear energy requirements of the sustainable development of the economy and society. Currently, there are about 22 nuclear power plant reactors are opening and the installed capacity is about 21000MWe. The total installed nuclear power capacity will achieve 58000MWe in 2020 and the installed capacity of nuclear power plants under...
Mr
KEMAL DOĞAN
(Turkish Atomic Energy Authority)
ORAL
Natural disaster occurred at Japan Fukushima Daiichi NPP in March 2011 showed that combination of natural disasters with a long term black out which is not accepted as a design basis accident till that day could be how dangerous. In this study, inventory calculation in the spent fuel pool, transmission from inventory to source term and atmospheric dispersion calculation of source term were...
Mr
Moustafa aziz Ibrahim
(head of nucleae safety department)
POSTER
Burnup credit is defined as the consideration of the reduction in reactivity associated with the use of the fuel in power reactors. Changes in the isotopic composition during fuel burnup which result in a reduced reactivity can be conveniently characterized by the reduction of the net fissile content, the build-up of actinides, the increase of the concentration of fission products, and the...
Mr
Junichi Kishimoto
(Mitsubishi Heavy Industries, LTD.)
ORAL
In Japan, the first interim spent fuel storage facility away-from-reactor (AFR) will start its operation for management of spent fuels until reprocessing. This facility stores BWR /PWR spent fuel assemblies using dry metal dual purpose casks (storage / transport) which will be transported to their destinations after the interim storage for decades. This facility is not equipped with a hot-cell...
Mr
Tatsuya Ishikawa
(Recyclable-Fuel Storage Company)
ORAL
Recyclable-Fuel Storage Company (RFS) has completed construction works of the storage building and fabrication works of several metal casks for spent fuels as the Japanese first off-site interim storage operator. RFS are now undertaking the safety review under new regulation standards based on the lesson learned by Fukushima-daiichi accident and preparing for the start of operation.
This...
Dr
Nader Mohamed
(Atomic Energy Authority, ETRR-2, Cairo, Egypt)
POSTER
Increasing the nuclear fuel burnup has a particular importance to improve the uranium utilization, to reduce the high level nuclear waste and to reduce the amount of plutonium in spent fuel per unit energy which improves the plutonium proliferation resistance.
This work is focused on strategies for direct recycling of 700 MWe Advanced CANDU Reactor (ACR-700) spent fuel in CANDU-6 reactor....
Dr
JOSE RAMON RAMIREZ SANCHEZ
(ININ)
POSTER
After the irradiation of the nuclear fuel, it is necessary to storage the fuel for cooling into the reactor pools, this is the first step of a series of process before reach his final destination.
Up to now there are two options more commonly adopted for the nuclear fuel cycle, one is the open cycle which requires a deep geological repository for final disposition of fuel. the other will be...
Dr
Andrew Newman
(Nuclear Threat Initiative), Prof.
Thomas Isaacs
(Nuclear Threat Initiative)
POSTER
Despite well-developed repository programs in Sweden, Finland and France, and encouraging progress in several other countries including Canada, the vast majority of states – including the U.S. – continue to struggle developing and implementing timely plans to safely and securely dispose of spent fuel and high level waste produced by nuclear power programs. Spent fuel continues to accumulate in...
Dr
Patrick Schwab
(U.S. Department of Energy)
POSTER
The Department of Energy (DOE) is laying the groundwork for implementing an integrated nuclear waste management disposition system. This includes preparing for future large-scale transport of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) since transport will be a necessary component of any integrated nuclear waste management disposition system. DOE continues to plan for and...
Mr
Ralph Stoll
(Predicus LLC (contractor for Argonne National Laboratory))
ORAL
The Nuclear Fuel Storage and Transportation Planning Project (NFST), under the U.S. Department of Energy, Office of Nuclear Energy, Office of Fuel Cycle Technology, is developing foundational capabilities to support the application of system engineering and decision analysis principles to inform future decisions regarding the deployment of a consolidated interim storage facility (ISF) for...
Dr
Annika Hagros
(Saanio & Riekkola Oy)
ORAL
In 2012, Posiva Oy submitted a construction licence for a spent fuel disposal facility to be constructed at Olkiluoto, Finland. A safety case (TURVA-2012) was compiled to support the licence application. The disposal concept is based on the KBS-3V method, where the spent fuel canisters are emplaced individually in vertical deposition holes. Posiva Oy is also studying, in collaboration with its...
Mr
Goto Masanori
(Hitachi Zosen Corporation)
ORAL
Mitigation of Saline Air Induced Stress Corrosion Cracking (SCC) is one of the big issues for aging management of spent fuel storage canisters made of austenite stainless steel for both long storage period and transportation after the storage. SCC is induced when three conditions, material (austenite stainless steel), saline air environment (salt deposit) and residual stress (surface tensile...
Mr
Dae-Sik Yook
(Korea Institute of Nuclear Safety)
POSTER
The future national policy for spent fuel management of Korea will be chosen based on the result of the public engagement, taking into consideration the national/international trends on policy and technology development. Based on this, the public engagement has started with the launch of the Public Engagement Commission on SNF management (PECOS) in 2013.
Regardless of the recommendation...
Dr
Matteo Mazzuccato
(European Commission, Joint Research Centre, Nuclear Decommissioning Unit)
POSTER
The Joint Research Centre (JRC) is currently involved in a Decommissioning and Waste Management (D&WM) Programme to progressively eliminate its historical liabilities related to the old nuclear installations and radiological waste used/generated in the past at Ispra site, inter alia: nuclear research reactors, hot-laboratories, radiochemical facilities and a variety of plants to treat and...
Ms
Madiha Afifi
(Abdel Samie Abdel Rahman)
POSTER
A proposed policy and strategy of the Arab Republic of Egypt towards the management of spent fuel from the nuclear power reactors is presented in this paper. The proposed Egyptian strategy supports the free international trade of nuclear materials and services and adheres to Non Proliferation Treaty (NPT) and other institutional frameworks aimed at promoting the peaceful use of nuclear power...
Ms
Päivi Maaranen
(senior inspector, Radiation and Nuclear Safety Authority in Finland, STUK)
ORAL
The objective of this presentation is to share regulator’s experiences of regulating and having oversight for the enlargement of a spent fuel interim storage. An overview of the current situation of spent fuel management and near future plans in Finland will be given.
In Finland, there are four operating reactors, one under the construction and two reactors that are waiting the construction...
Mr
Arturas Smaizys
(Lithuanian Energy Institute)
ORAL
The present spent nuclear fuel management concept in the Lithuania foresees dry spent nuclear fuel storage in the casks for 50 years. During this time the final management concept shall be developed. Different options are under consideration, however due to various uncertainties in future, there is a risk that these options can be not implemented in due time, therefore elongation of the spent...
Dr
KOJI SHIRAI
(Central Research Institute of Electric Power Industry (CRIEPI))
ORAL
The CRIEPI (Central Research Institute of Electric Power Industry) has executed several study programs on demonstrative testing for interim storage of spent fuel, related to metal cask storage technology to reflect in Japanese safety requirements for dry casks.
If a metal gasket used in a dual purpose metal cask was subjected to high temperature for a long term, the residual linear loads and...
Mrs
Tatiana Makarchuk
(Rosatom/Federal Center for Nuclear and Radiation Safety)
ORAL
A new technology of spent nuclear fuel (SNF) management at the back-end of the fuel cycle has been developed over the last twenty years. This technology is based on the concept of the shielded cask ensuring containment of its contents (SNF) and compliance with all other requirements for SNF storage and transport. Radiation protection and activity containment are ensured by physical barriers,...
Mr
DAVID GARRIDO QUEVEDO
(EQUIPOS NUCLEARES SA (ENSA))
ORAL
One of the safety-related functions in a DPC is the thermal performance. Regulations only address a thermal test to assure the cask thermal performance under accident conditions (fire test). As a DPC is also to be used for storage, the thermal passive behavior of the cask under normal condition of storage shall be demonstrated.
Although this thermal test is not included in storage...
Mr
Horacio Luna Davila
(Comisión Nacional de Enería Atomica)
POSTER
Atucha I NPP was started up in 1974 initiating the nuclear energy production in Argentina. It is a HWR pressure vessel type of 350 Mw. With the purpose of solving the current situation that both fuel pools capacity will be soon complete (Pool Buildings I and II) and considering the future life extension of the Plant, CNEA was asked to develop a project integrating systems in a new building...
Mr
Tsutomu HIROSE
(Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))
ORAL
It is assumed that the characteristics of high burnup fuel, such as the increase of hydrogen contents and hydrides radially precipitated in cladding, would affect the fuel integrity at cask drop accident during dry storage and transport.
For the assessment of high burnup spent fuel integrity at the cask drop accident, the mechanical behavior of the fuel rod such as deformation, failure and...
Mr
Jiří Gerža
(ČEZ, a.s., NPP Dukovany)
ORAL
The first Czech Nuclear Power Plant, NPP Dukovany, has almost reached 30 years of safe operation. Significant amount of spent fuel has been produced, though a number of fuel cycle improvements helped to increase fuel performance and decrease its quantity. During the operation years, spent fuel management had to respond to many changes, both political and technical. We had to leave an option to...
Mr
Mustapha Chiguer
(Conference Participant)
ORAL
Used Fuel Management is more and more one of the major topics that nuclear countries and utilities have to face when managing existing nuclear power plant as well as new build.
Stakeholders concerns are growing in parallel of the steady increase of used fuel inventories due to fading away of the back-end endpoint in most nuclear countries.
Utilities are additionally being challenged...
Mr
Iurie Bosneaga
(Institute of Applied Physics of Academy of Sciences of Moldova)
POSTER
Nowadays nuclear power is based on the usage of exothermic nuclear processes. Actually it means that the thermal engine principle of heat conversion into mechanical work is used - with the respective thermodynamic limitation of maximal efficiency (by Carnot cycle). The only difference is that heat is obtained due to nuclear fuel “burning” - instead of traditional fossil fuel burning. As a...
Ms
Miriam Lloret
(ENUSA Industrias Avanzadas)
ORAL
In Spain, the fuel is stored in the spent fuel pools and in on-site interim dry storage facilities when the pool capacity is reached. Additionally, a centralized temporary storage facility to dry store spent fuel assemblies, based in a vault system, is under construction.
Fuel conditions (internal and external pressure, temperature, etc) differs from pool to dry storage. The morphology and...
Ms
Julia Palmes
(Bundesamt fuer Strahlenschutz)
ORAL
Since the concept of dry interim storage of spent nuclear fuel elements in transport casks had been developed by the former DWK in the late 1970s and had been first evaluated by the RSK (Reaktor-Sicherheitskommission) in 1979, development has been going on. Dry interim storage passed a lot of modifications in different fields, but the fundamentals of this first concept – on which the dual...
Ms
Sylvia Saltzstein
(Sandia National Labs)
ORAL
In 2009 the United States made a decision to discontinue pursuing a license for a long-term geologic repository for used nuclear fuel. Until another license is pursued, used nuclear fuel will accumulate and remain in dry storage for longer than originally planned. At the end of 2013, the US had over 22,000 Metric Tons Uranium (Initial) of used nuclear fuel in 1850 dry storage casks, stored...
Mr
Matthew Feldman
(Oak Ridge National Laboratory)
POSTER
The US Department of Energy Office of Nuclear Energy established the Nuclear Fuels Storage and Transportation Planning Project to lay the groundwork for implementing an interim storage facility, including associated transportation activities. Efforts include the development of a system for the large-scale transport of spent nuclear fuel that will be necessary in an integrated waste management...
Mr
David Hambley
(National Nuclea r Laboratory)
ORAL
Worldwide, slow progress in the deployment of geological disposal facilities and reduced use of reprocessing has led to the need to increase the inventory and duration of spent fuel storage. This has led to a range of approaches to the management of spent fuel in storage being adopted in different countries. A review has been undertaken to identify learning from the different approaches...
Dr
Holger Völzke
(BAM Federal Institute for Materials Research and Testing)
ORAL
The safe and secure storage of spent nuclear fuel and high-level waste from nuclear power reactors is one of the major long-term issues to be solved in the nuclear business. Today no country has a repository available for final disposal or in some countries reprocessing capacities for spent fuel are not sufficiently available as planned. In the meantime the safe interim storage for the...
Dr
Paolo Finocchiaro
(Istituto Nazionale di Fisica Nucleare - Laboratori Nazionali del Sud)
POSTER
A low-cost array of modular sensors for online monitoring of radioactive waste was developed at INFN-LNS. We implemented a new kind of gamma counter, based on Silicon PhotoMultipliers and scintillating fibers, that behaves like a cheap scintillating Geiger-Muller counter. Front-end electronics and an FPGA-based counting system were developed to handle the field data, also implementing data...
Dr
Yung Liu
(Argonne National Laboratry)
ORAL
In the United States, there is currently no designated disposal site for used nuclear fuel, which raises the prospect of extended long-term storage (i.e., >60 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations 72.42, the initial license term for an...
Dr
Evaristo Jose Bonano
(Sandia National Laboratories)
ORAL
Management of spent nuclear fuel (SNF), produced from nuclear reactors, consists of three main components: storage, transportation, and disposal. Of these three components, disposal is not occurring in the United States (US) and transportation has occurred on an intermittent basis. Short-term storage of commercial SNF generally occurs in either the reactor pool or dry storage casks on the...
Dr
Kanokrat TIYAPUN
(Thailand Institute of Nuclear Technology)
POSTER
The spent fuel storage of TRIGA reactor (TRR-1/M1) was designed. Detailed criticality safety analysis was conducted according to the basic safety standard and within the framework of the regulatory aspect. The Monte Carlo computer code (MCNP) was used for the detailed geometry modeling. Two types of fuel elements were considered for the calculation including 8.5 wt% and 20 wt% fuel elements....
78.
Mechanical Properties of Aluminium Alloys for Transport and Storage Cask after Long Term Storage
Mr
Junichi Kishimoto
(Mitsubishi Heavy Industries, LTD.)
ORAL
In recent dry transport and storage dual-purpose cask designs for spent nuclear fuel, various kinds of aluminium alloy are widely used for basket material as a structural member. Basket for dual-purpose cask is designed to maintain prescribed geometrical arrangements of spent fuel assemblies under accidents during transport and storage conditions, and also designed to have thermal performance...
Mr
Yuriy Fedorov
(Khlopin Radium Institute, St-Petersburg, Russia)
ORAL
The report covers REMIX fuel consumption in VVER-1000. REMIX fuel is fabricated from inseparated mixture of uranium and plutonium obtained during NPP spent fuel reprocessing with further makeup by enriched natural uranium. It makes possible to recycle several times the total amount of uranium and plutonium obtained from spent fuel with 100% loading of the WWER-1000 core. The stored SNF could...
Dr
Juan Maria Garcia de la Infanta Belio
(Spent Fuel - Development and Equipments Technology - ENUSA Industrias Avanzadas)
ORAL
ENUSA, the Spanish nuclear fuel manufacturer since the 1980s, is the main specialist in Spain of LWR nuclear fuel design and performance. During this time, ENUSA has acquired deep knowledge and experience on the fuel assemblies burned by its customers, and currently stored in the spent fuel pools. Eventually, ENUSA has also specialized in spent fuel management, offering integrated engineering...
Mr
Ilia Kuzmin
(Sosny R&D Company)
POSTER
A peculiarity of the RBMK reactors is online core refueling. So, the core contains fuel assemblies with burnup varying from zero to the maximum design value. When the reactor is shut down for decommissioning, the quantity of the fuel assemblies that have not reached the maximum design burnup may be significant. In 2018 – 2035, the design lifetime of the RBMK reactors operated in Russia will...
Dr
Matthias Jaunich
(BAM Federal Institute for Materials Research and Testing)
ORAL
Elastomer seals are widely used as barrier seals in containers for low and intermediate level radioactive waste and for spent fuel transportation casks. In addition, they are also used for spent fuel storage and transportation casks (dual purpose casks (DPC)) as auxiliary seals to allow leakage rate measurements of metal barrier seals for demonstration of their proper assembling conditions....
Prof.
Lan Zhang
(Shanghai Institute of Applied Physics, Chinese Academy of Sciences), Dr
Yuxia Liu
(Shanghai Institute of Applied Physics, Chinese Academy of Sciences)
POSTER
In order to make full use of the rich resources of thorium, a new nuclear reactor-TMSR (thorium molten salt reactor) was proposed. In this reactor, the molten mixture of ThF4, UF4 and LiF-BeF2 was used.
Now we are trying to develop a totally new flowsheet for TMSR spent fuel processing in which pyrohydrolytic technology is included. Pyrohydrolysis was first introduced by Warf et al. in the...
Dr
Toshiari Saegusa
(Executive Research Scientist, CRIEPI)
ORAL
Efficient spent fuel management (SFM) requires an evaluation of the potential interface issues among phases of the nuclear fuel life cycle: including: technical disconnects, policy considerations, and varied positions of the many stakeholders that influence management options and decisions. Because many issues affect multiple stakeholders and may require long lead times to resolve, it is...
Mr
Sergey Sklyarov
(All-Russia Research Institute of Automatics (VNIIA))
POSTER
One of the most important characteristic of a “closed” fuel cycle is a limitation of actinide losses by 0.1% level. The work demonstrates a possibility to control the above parameter via the differential die-away technology in case of high gamma background that may be caused by fission products of spent fuel. The preliminary results obtained by the experimental set-up based on this technology...
Dr
Jeong Hun Cha
(Korea Institute of Nuclear Safety(KINS))
POSTER
It is expected that amount of nuclear spent fuels will exceed the capacity of temporary storage tanks in each nuclear power plant in Korea after several years. Accordingly, the industry demand for storage cask commercialization has been increased. According to the demand, KINS(Korea Institute of Nuclear Safety) started to develop a thermal technical guidelines including CFD analysis as a...
Mr
Bambang Eko ARYADI
(Nuclear Energy Regulatory Agency of INDONESIA (BAPETEN))
POSTER
Upon the operation of 3 research reactors and there are plans for the construction of nuclear power plants, Indonesia needs to provide a regulatory framework governing the management of spent nuclear fuel from these two types of reactors. For that reasosn Indonesia has a set of rules that govern it, management of nuclear spent fuel has been regulated in the law and the supporting regulations...
Mr
Matthew Gordon
(U.S. Nuclear Regulatory Commission (USNRC))
ORAL
The U.S. Nuclear Regulatory Commission (USNRC) risk-informs a variety of operating and new nuclear reactor regulatory activities. This practice is rooted in probabilistic risk assessment (PRA), a highly detailed, quantitative method. Significant resources are required to develop PRA models for reactors, however. The USNRC’s Division of Spent Fuel Management (SFM) is developing a...
Mr
Sergey Perepelkin
(Sosny R&D Company)
ORAL
The RBMK-1000 power reactors have been operated at Leningrad, Kursk and Smolensk NPPs in the European part of Russia. The yearly fuel discharge from the RBMK-1000 reactors makes up 3500 SFAs placed in reactor cooling pools and separate spent fuel wet storage facilities at NPPs. Since 2011, in accordance with Rosatom's con-cept the RBMK SNF has been converted to safer dry storage in a...
Dr
Svitlana Alyokhina
(National Academy of Sciences of Ukraine)
POSTER
More than 250 tons of spent nuclear fuel is produced by Ukrainian NPPs each year. Currently the problem of spent nuclear fuel storage in Ukraine is under process of solving. The temporary storage of SNF until accepting decision about disposal or reprocessing today is used for six WWER-1000 reactors of Zaporizhska NPP.
The Dry Spent Nuclear Fuel Storage Facility (DSNFSF) on Zaporizhska NPP is...
Dr
Sanghoon Lee
(Korea Atomic Energy Research Institute)
POSTER
In preparation for the timely installation of interim storage facility for spent nuclear fuel (SF), Korea Radioactive Waste Agency (KORAD) is developing domestic models of SF storage systems, and the concrete storage cask is one of them. A concrete cask consists of a metallic canister, which confines SF with welded closure and a concrete overpack, which provides radiation shielding and...
Mrs
Anzhelika Khaperskaya
(State Corporation ROSATOM)
ORAL
SNF Management Concept of the State Atomic Energy Corporation ROSATOM is in place in the Russian Federation. The Concept specifies goals and strategic vector of SNF management.
The Russian Federation policy in the field of SNF management is based on the principle of SNF procession in order to ensure ecologically acceptable handling of fission products and return of regenerated nuclear...
Mr
Gerold Hermann Spykman
(TÜV NORD EnSys Hannover GmbH & Co. KG)
ORAL
Beside the long term behavior of the fuel itself the cladding behavior is an important issue for interim and long term storage of spent fuel in casks. In dry storage the fuel rod cladding is important for the retention of fission products. It is still the first barrier even if the storage casks are designed to contain the fission products during the designated storage period. In Germany the...
Prof.
Mohamed Abdel Geleel
(Head of Nuclear Fuel Cycle Department)
POSTER
Spent fuel is generated continually by operating nuclear reactors. It is stored in the reactor fuel storage pool for a period of time for cooling and then may be transferred to a designated wet or dry spent fuel storage facility, where it will await reprocessing or disposal (if it is considered to be radioactive waste). The spent fuel storage pools of some reactors have sufficient capacity to...
Mr
Ray Kellar
(U.S. Nuclear Regulatory Commission)
ORAL
Within the United States, the Nuclear Regulatory Commission (NRC) has the responsibility for licensing and inspection of spent fuel storage operations. This includes storage in the spent fuel pool, typically licensed under Title 10 Code of Federal Regulations (CFR) Part 50 regulations, and within spent fuel cask systems licensed by 10 CFR Part 72 regulations. The spent fuel cask systems are...
Mr
Manfred Richter
(NUKEM Technologies Engineering Services GmbH)
ORAL
One pre-condition for Lithuania to join the European Union (EU) in 2004 was to shut down the Ignalina Nuclear Power Plant (INPP). The power plant has two RMBK type water cooled graphite moderated pressure tube reactors each of design capacity 1500MW(e) which started operation in 1983 respective in 1987. To fulfil this requirement, it was decided that Ignalina NPP several decommissioning...
Mr
HIDEKI YAGIHASHI
(Nuclear Regulation Authority)
POSTER
In Japan, a need for additional spent fuel storage capacity is increasing due to a decrease in the residual storage capacity of at reactor (AR) spent fuel pools. The Japan’s first away from reactor (AFR) dry storage facility for spent fuel, the Recyclable Fuel Storage Center in Mutsu-shi, Aomori, has completed its construction, and dry storage using Dual Purpose Casks (DPC) in this facility is...
Prof.
Bernard BOULLIS
(CEA, Nuclear Energy Division, Director for back-end)
ORAL
France has deployed from the late 1970’s a fleet of large water reactors (63 GWe within about 20 years, due to French government decisions in the early seventies); and, in the same time, fuel cycle industrial facilities have been launched to deserve a closed fuel cycle policy. The main drivers for reprocessing and recycling strategy were to take advantage of valuable content of used fuels,...
Ms
Melissa Bates
(U.S. Department of Energy)
ORAL
The United States (US) is interested in demonstrating the ability to safely store — for many decades — and then transport spent nuclear fuel (SNF). The potential need to store SNF for many decades will have a near-term and potentially significant impact on US nuclear plant licensing and operations. While dry storage of lower burnup SNF [less than 45 gigawatt days per metric ton uranium...
Mr
Rod McCullum
(Nuclear Energy Institute (U.S.))
ORAL
On September 19, 2014 the United States Nuclear Regulatory Commission (NRC) published its final rule and supporting Generic Environmental Impact Statement (GEIS) on Continued Storage of Spent Nuclear Fuel. This action, motivated by a U.S. Court mandate following the termination of the Yucca Mountain Repository project, marked a significant shift in U.S. regulatory policy. Previously, since...
Mr
Matthew Feldman
(Oak Ridge National Laboratory)
POSTER
In the United States, the American National Standards Institute (ANSI) facilitates the development of American National Standards by accrediting the procedures of standards developing organizations, also known as SDOs. Accredited Standards Committee (ASC) N14, “Packaging and Transport of Radioactive and Non-Nuclear Hazardous Materials,” is the ANSI-accredited SDO that publishes standards for...
Dr
SUNG IL KIM
(Korea Institute of Nuclear Safety)
POSTER
This study examined the current status of spent fuel management in Korea and the process of building public opinion that is currently underway to determine the final national policy for spent fuel.
Spent fuels generated in the PWR plants are stored in a spent fuel pool for each unit. To date, almost all PWR plants continue to implement measures to address the lack of storage capacity such as...
Mr
robert Howard
(Oak Ridge National Laboratory)
POSTER
The Nuclear Fuels Storage and Transportation Planning Project, under the US Department of Energy Office of Nuclear Energy Fuel Cycle Technologies program, is developing tools and techniques, gathering data and information, and conducting analyses to inform future decisions regarding the waste management system. Spent Nuclear Fuel (SNF) management system analysis, systems engineering, and...
Mr
Juraj Vaclav
(Nuclear Regulatory Authority of the Slovak Republic)
ORAL
In Slovakia we use nuclear energy for more than forty years. In the past spent fuel was transported to former Soviet Union. Since 1987 we store all spent fuel in Interim Spent Fuel Facility at Bohunice site. So the spent fuel is stored before its final deposition or reprocessing. For transport of spent fuel we use transport container C-30. The paper describes thermal calculations of C-30.
The...
Prof.
Lorena Pilar Rodriguez Garcia
(The Higher Institute of Technologies and Applied Sciences, Faculty of Nuclear Sciences and Technologies)
POSTER
The current growth of the energy demand, the perspective of a pronounced increment for the next future, added to the near depletion of the fossil fuels has made finding sustainable alternatives of energy supply, a challenge to the international scientific community. Nuclear Energy is presented as a prominent energy source because nuclear energy is a clean, safe, and cost-effective energy...
Dr
Ingo Reiche
(German Federal Office for Radiation Protection (BfS))
ORAL
There are different concepts for management of spent nuclear fuel, including wet storage in pools and dry storage in welded canisters or in dual-purpose transport and storage casks. But all of them require transport of the spent fuel, at least transport to the final destination after the interim storage period. This presentation analyzes how this safe transport of spent fuel after several...
Mr
Vladimir Chrapciak
(senior engineer)
ORAL
The transport cask C-30 with basket T-12 was developed in former East Germany for VVER-440 fuel with enrichment 3.6%. Later was in Slovakia developed the new compact basket KZ-48 for VVER-440 fuel with enrichment 4.4% and maximal burnup 55 MWd/kgU. The present licence is for VVER-440 fuel with enrichment 4.4% and maximal burnup 60 MWd/kgU. The future licence need to be for VVER-440 fuel with...
Dr
Deni G. Priyanto Putro
(Canadian Nuclear Laboaratories)
ORAL
A comprehensive research and development program of geologic characterization and large-scale geotechnical experiments in granite was undertaken at Canada’s Underground Research Laboratory (URL) starting in 1980 to evaluate the concept of permanent disposal of used CANDU® fuel in a deep geological repository (DGR) constructed in Canadian Shield granite. Before the underground facility was...
Mr
Steven Jones
(U.S. Nuclear Regulatory Commission)
POSTER
Following the challenges to wet storage of spent fuel during the events at Fukushima, the U.S. Nuclear Regulatory Commission (NRC) evaluated whether the reduced density of spent fuel in at-reactor wet storage would provide a substantial enhancement in safety. The reduced storage density would be achieved through expedited transfer of fuel to dry storage such that only fuel with less than 5...
Dr
Chang Hwa Lee
(Korea Atomic Energy Research Institute)
ORAL
Zirconium (Zr)-alloys such as Zircaloy and Zirlo have been widely used as cladding tube materials for nuclear fuel assembly due to its low absorption cross-section to thermal neutrons, high hardness, ductility, and corrosion resistance. The Zr-alloy cladding hull wastes are expected to be generated from the pretreatment step of recycling technologies such pyroprocess or of long-term storage...
