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Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel
Standard Review Plan for Transportation Packages for MOX Spent Nuclear Fuel
The NRC contracted with LLNL to compile this supplement to NUREG-1617 to incorporate additional
information specific to mixed uranium-plutonium oxide (MOX) fuel. This supplement provides details
on package review guidance resulting from significant differences between spent nuclear fuel from
irradiated LEU fuel and that from irradiated MOX fuel. The information presented is not to be
construed as having the force and effect of NRC regulations (except where regulations are cited), or as
Spent Fuel Burnup Credit in Casks: An NRC Perspective
Spent Fuel Burnup Credit in Casks: An NRC Perspective
Until now, the Nuclear Regulatory Commission's (NRC) approval of criticality safety evaluations for spent fuel in transport and storage casks has been based on analyzing the fuel as though it were fresh and without burnable poisons. The well-known nuclide composition of fresh fuel has provided a straightforward and bounding approach for showing that spent fuel systems will remain subcritical under normal and accident conditions. Burnup credit refers to the approval of criticality safety evaluations that consider the decrease in fuel reactivity caused by. irradiation in the reactor.
Selection of Reactor Criticals as Benchmarks for Spent Nuclear Fuels
Selection of Reactor Criticals as Benchmarks for Spent Nuclear Fuels
An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel
An Empirical Approach to Bounding the Axial Reactivity Effects of PWR Spent Nuclear Fuel
One of the significant issues yet to be resolved for using
burnup credit ~BUC! for spent nuclear fuel ~SNF! is establishing
a set of depletion parameters that produce an adequately conservative
representation of the fuel’s isotopic inventory. Depletion
parameters ~such as local power, fuel temperature, moderator temperature,
burnable poison rod history, and soluble boron concentration!
affect the isotopic inventory of fuel that is depleted in a
pressurized water reactor ~PWR!. However, obtaining the detailed
Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application
Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application
Criticality safety analysis devoted to spent-fuel storage and transportation has to be conservative in order to be sure no accident will ever happen. In the spent-fuel storage field, the assumption of freshness has been used to achieve the conservative aspect of criticality safety procedures. Nevertheless, after being irradiated in a reactor core, the fuel elements have obviously lost part of their original reactivity. The concept of taking into account this reactivity loss in criticality safety analysis is known as burnup credit.
Computational Benchmark of SAS2D Against Spent Fuel Samples from the Takahama-3 Reactor
Computational Benchmark of SAS2D Against Spent Fuel Samples from the Takahama-3 Reactor
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
The effect of fixed absorbers on the reactivity of pressurized water reactor (PWR) spent nuclear fuel (SNF) in support of burnup-credit criticality safety analyses is examined. A fuel assembly burned in conjunction with fixed absorbers may have a higher reactivity for a given burnup than an assembly that has not used fixed absorbers. As a result, guidance on burnup credit, issued by the U.S. Nuclear Regulatory Commission's Spent Fuel Project Office, recommends restricting the use of burnup credit to assemblies that have not used burnable absorbers.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report under the Joint Convention by the Government of the Federal Republic of Germany for the Second Review Meeting in May 2006
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Report under the Joint Convention by the Government of the Federal Republic of Germany for the Second Review Meeting in May 2006
The Federal Government will continue to meet Germany’s existing international obligations, par- ticularly with regard to fulfilment of the Joint Convention. In submitting this report, the Federal Re- public of Germany is demonstrating its compliance with the Joint Convention and ensuring the safe operation of facilities for the management of spent fuel and radioactive waste, including the de- commissioning of nuclear installations. At the same time, there is still a need for future action in order to maintain the required high standards of safety and ensure disposal.
Generic Repository Design Concepts and Thermal Analysis (FY11)
Generic Repository Design Concepts and Thermal Analysis (FY11)
Reference concepts for geologic disposal of used nuclear fuel and high-level radioactive waste in
the U.S. are developed, including geologic settings and engineered barriers. Repository thermal
analysis is demonstrated for a range of waste types from projected future, advanced nuclear fuel
cycles. The results show significant differences among geologic media considered (clay/shale,
crystalline rock, salt), and also that waste package size and waste loading must be limited to meet
targeted maximum temperature values.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, October 2005
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Australian National Report, October 2005
The responsibility for the governance of Australia is shared by the Australian government and the governments of the six states and two self governing territories. Responsibility for radiation health and safety in each State and Territory rests with the respective State/Territory government, unless the activity is carried out by an Australian government agency or a contractor to a Australian government agency; in those cases the activity is regulated by the Australian government.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Austrian National Report
In Austria there is neither a nuclear power plant (NPP) nor any other fuel cycle facility in op- eration. One NPP was constructed in Zwentendorf in the 1970s, but, as a consequence of the negative vote in a referendum never put into operation. Two out of three research reactors in Austria have been shut down (ASTRA Seibersdorf in 2000, SIEMENS Argonaut Graz in 2004) and are currently under decommissioning. The remaining TRIGA research reactor in Vienna is still in operation. Spent nuclear fuel is stored on site in wet or dry storage facilities.
NRC SFST ISG-8: Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks
NRC SFST ISG-8: Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transportation and Storage Casks
Title 10 of the Code of Federal Regulations (10 CFR) Part 71, Packaging and Transportation of
Radioactive Material, and 10 CFR Part 72, Licensing Requirements for the Independent
Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater
Than Class C Waste, require that spent nuclear fuel (SNF) remain subcritical in transportation
and storage, respectively. Unirradiated reactor fuel has a well-specified nuclide composition
that provides a straightforward and bounding approach to the criticality safety analysis of
Questions and Answers to the National Report of the Czech Republic
Questions and Answers to the National Report of the Czech Republic
Questions and Answers to the National Report of the Czech Republic
Joint Convention Questions Posted to Denmark in 2006
Joint Convention Questions Posted to Denmark in 2006
Joint Convention Questions Posted to Denmark in 2006
Transportation of Commercial Spent Nuclear Fuel Regulatory Issues Resolution
Transportation of Commercial Spent Nuclear Fuel Regulatory Issues Resolution
The U.S. industry’s limited efforts at licensing transportation packages characterized as “highcapacity,”
or containing “high-burnup” (>45 GWd/MTU) commercial spent nuclear fuel
(CSNF), or both, have not been successful considering existing spent-fuel inventories that will
have to be eventually transported. A holistic framework is proposed for resolving several CSNF
transportation issues. The framework considers transportation risks, spent-fuel and cask-design
International Review Team Report: A Peer Review of the Yucca Mountain IMARC Total System Performance Assessment EPRI Model
International Review Team Report: A Peer Review of the Yucca Mountain IMARC Total System Performance Assessment EPRI Model
Since 1989, EPRI has been conducting independent assessments of the proposed deep geologic repository for the disposal of spent nuclear fuel and high level radioactive waste at Yucca Mountain, Nevada. EPRI pioneered application of the total system performance assessment (TSPA) approach for evaluating performance of geologic repository systems on a probabilistic basis. Along the way, EPRI developed the Integrated Multiple Assumptions and Release Code (IMARC) as its primary analytical tool for TSPA-based evaluations.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Ireland National Report, May 2003
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Ireland National Report, May 2003
There are no nuclear power stations and no nuclear fuel cycle activities in Ireland. There are 2.5 tonnes of natural uranium in storage on the campus of a university, which was previously incorporated in a sub-critical assembly. This material is stored in the building in which it was previously used. Other than in relation to these uranium sources, the application of the Convention is limited to radioactive waste arising from the medical, industrial and research applications of radioisotopes.
EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs
EPRI Review of Geologic Disposal for Used Fuel and High-Level Radioactive Waste: Volume III --Review of National Repository Programs
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has left the U.S. program for management of used fuel and high level radioactive waste (HLW)
in a state of uncertainty. In concert with this major policy reset and in response to the resulting
policy vacuum, the President directed the Energy Secretary to establish the Blue Ribbon
Commission on America’s Nuclear Future (BRC) “…to conduct a comprehensive review of
policies for managing the back end of the nuclear fuel cycle and to provide recommendations for
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume I --The U.S. Site Selection Process Prior to the Nuclear Waste Policy Amendments Act
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume I --The U.S. Site Selection Process Prior to the Nuclear Waste Policy Amendments Act
U.S. efforts to site and construct a deep geologic repository for used fuel and high level radioactive waste (HLW) proceeded in fits and starts over a three decade period from the late 1950s until 1982, when the U.S. Congress enacted the Nuclear Waste Policy Act (NWPA). This legislation codified a national approach for developing a deep geologic repository. Amendment of the NWPA in 1987 resulted in a number of dramatic changes in direction for the U.S. program, most notably the selection of Yucca Mountain as the only site of the three remaining candidates for continued investigation.
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume II --U.S. Regulations for Geologic Disposal
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume II --U.S. Regulations for Geologic Disposal
U.S. efforts to site and construct a deep geologic repository for used fuel and high level
radioactive waste (HLW) proceeded in fits and starts over a three decade period from the late
1950s until 1982, when the U.S. Congress enacted the Nuclear Waste Policy Act (NWPA). This
legislation codified a national approach for developing a deep geologic repository. Amendment
of the NWPA in 1987 resulted in a number of dramatic changes in direction for the U.S.
program, most notably the selection of Yucca Mountain as the only site of the three remaining
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report by Ireland, October 2005
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report by Ireland, October 2005
This Report gives an outline of Ireland’s national policy, State institutional framework and general legislation governing all aspects of the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in Ireland. It also sets out measures adopted to implement the relevant obligations of the Convention noting that Ireland does not have any spent nuclear fuel to deal with.
Occupational Risk Consequences of the Department of Energy's Approach to Repository Design, Performance Assessment, and Operation in the Yucca Mountain License Application
Occupational Risk Consequences of the Department of Energy's Approach to Repository Design, Performance Assessment, and Operation in the Yucca Mountain License Application
EPRI has discovered several aspects of the U.S Department of Energy (DOE) proposed design and operation of the Yucca Mountain repository that—if implemented as described in the license application (LA)—could result in unnecessary occupational health and safety risk to workers involved with repository-related activities. This report identifies key DOE conservatisms and focuses on the occupational risk consequences of the DOE's approach to the repository design, performance assessment, and operation.