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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.
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.
Dry Transfer System for Spent Fuel: Project Report: A System Designed to Achieve the Dry Transfer of Bare Spent Fuel Between Two Casks
Dry Transfer System for Spent Fuel: Project Report: A System Designed to Achieve the Dry Transfer of Bare Spent Fuel Between Two Casks
Use of an on-site dry transfer system (DTS) allows utilities with limited crane capacities or other plant restrictions to take advantage of large efficient storage systems. By using this system, utilities can also transfer fuel from loaded storage casks to transport casks without returning to their fuel storage pool.
Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems
Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems
Due to the delayed opening of a final geological repository for spent nuclear fuel, the lifespan of dry cask storage systems may be increased to 120 years or longer. To ensure safety over this extended period of interim storage, degradation mechanisms that have the potential to cause penetration of the canister confinement boundary must be evaluated and understood.
NRC SFST ISG-2: Fuel Retrievability
NRC SFST ISG-2: Fuel Retrievability
This Interim Staff Guidance (ISG) provides guidance to the staff for determining if
storage systems to be licensed under 10 CFR Part 72 allow ready retrieval of spent fuel.
This guidance is not a regulation or a requirement.
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
NRC SFST ISG-9: Storage of Components Associated with Fuel Assemblies
NRC SFST ISG-9: Storage of Components Associated with Fuel Assemblies
The purpose of this ISG is to clarify the technical criteria for types of materials that will be |
considered associated with the storage of spent fuel assemblies. While control rods are |
mentioned in the Standard Review Plan as possible contents, specific information and guidance
is lacking.
Revision 1
NRC SFST ISG-10: Alternatives to the ASME Code
NRC SFST ISG-10: Alternatives to the ASME Code
There is no existing American Society of Mechanical Engineers (ASME) Code for the design
and fabrication of spent fuel dry storage casks. Therefore, ASME Code Section III, is
referenced by NUREG-1536, “Standard Review Plan for Dry Cask Storage Systems,” as an
acceptable standard for the design and fabrication of dry storage casks. However, since dry
storage casks are not pressure vessels, ASME Code Section III, cannot be implemented
without allowing some alternatives to its requirements.
Revision 1
NRC SFST ISG-11: Cladding Considerations for the Transportation and Storage of Spent Fuel
NRC SFST ISG-11: Cladding Considerations for the Transportation and Storage of Spent Fuel
The staff has broadened the technical basis for the storage of spent fuel including assemblies
with average burnups exceeding 45 GWd/MTU. This revision to Interim Staff Guidance No. 11
(ISG-11) addresses the technical review aspects of and specifies the acceptance criteria for
limiting spent fuel reconfiguration in storage casks. It modifies the previous revision of the ISG
in three ways: (1) by clarifying the meaning of some of the acceptance criteria contained in
NRC SFST ISG-14: Supplemental Shielding
NRC SFST ISG-14: Supplemental Shielding
Guidance regarding supplemental shielding that may be installed at an independent
spent fuel storage installation (ISFSI) to meet the requirements of 10 CFR 72.104(a).
NRC SFST ISG-17: Interim Storage of Greater Than Class C Waste
NRC SFST ISG-17: Interim Storage of Greater Than Class C Waste
Guidance is necessary on the interim storage of greater than Class C (GTCC) waste due to the
revision of Title 10 of the Code of Federal Regulations (10 CFR) Part 72. The revision to 10
CFR Part 72 is documented in final rule, ìInterim Storage for GTCC Waste,î and permits the
storage of GTCC wastes at independent spent fuel storage installations (ISFSI) or monitored
retrievable storage (MRS) facilities. The GTCC wastes, if stored at an ISFSI, must be in solid
form, and stored in a separate container (i.e., GTCC waste may not be stored in a cask that
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
NRC SFST ISG-18: The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage
NRC SFST ISG-18: The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage
The purpose of this ISG is to address the design and testing of the various closure welds (“lid
welds”) associated with the redundant closure of all-welded austenitic stainless steel canisters:
As an acceptable confinement boundary under 10 CFR Part 72.236(e) (Ref. 1) for
purposes of demonstrating no credible leakage of radioactive material during storage
and satisfying the dose limits under normal and off-normal conditions in 10 CFR Parts
72.104(a) and 72.106(b).
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
Industry Spent Fuel Storage Handbook
Industry Spent Fuel Storage Handbook
The Industry Spent Fuel Storage Handbook (“the Handbook”) addresses the relevant aspects of at-reactor spent (or used) nuclear fuel (SNF) storage in the United States. With the prospect of SNF being stored at reactor sites for the foreseeable future, it is expected that all U.S. nuclear power plants will have to implement at-reactor dry storage by 2025 or shortly thereafter. The Handbook provides a broad overview of recent developments for storing SNF at U.S. reactor sites, focusing primarily on at-reactor dry storage of SNF.
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 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
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV - Lessons Learned
EPRI Review of Geologic Disposal for Used Fuel and High Level Radioactive Waste: Volume IV - Lessons Learned
The effective termination of the Yucca Mountain program by the U.S. Administration in 2009 has further delayed the construction and operation of a permanent disposal facility for used fuel and high level radioactive waste (HLW) in the United States. In concert with this decision, the President directed the Energy Secretary to establish the Blue Ribbon Commission on America's Nuclear Future to review and provide recommendations on options for managing used fuel and HLW.
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Technical Bases for Extended Dry Storage of Spent Nuclear Fuel
Independent spent fuel storage installations (ISFSIs) are currently licensed for 20 years. However, delays in developing permanent spent fuel disposal capability require continued ISFSI storage beyond the 20-year term. This report provides a technical basis for demonstrating the feasibility of extended spent fuel storage in ISFSIs.
Yucca Mountain Licensing Standard Options for Very Long Time Frames: Technical Bases for the Standard and Compliance Assessments
Yucca Mountain Licensing Standard Options for Very Long Time Frames: Technical Bases for the Standard and Compliance Assessments
In the existing U.S. Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations governing the spent nuclear fuel and high-level radioactive waste site at Yucca Mountain, Nevada, the time period of compliance was set at 10,000 years. Recently, a Court ordered that EPA and NRC either revise the regulation on this topic to be "based upon and consistent with" recommendations made by a panel of the National Academy of Sciences, who recommended a time period of compliance out to as long as one million years, or seek congressional relief.