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Dry Storage of Used Fuel Transition to Transport
Dry Storage of Used Fuel Transition to Transport
This report provides details of dry storage cask systems and contents in U.S. for commercial light water
reactor fuel. Section 2 contains details on the canisters used to store approximately 86% of assemblies in
dry storage in the U.S. Transport cask details for bare fuels, dual purpose casks and canister transport
casks are included in Section 3. Section 4 details the inventory of those shutdown sites without any
operating reactors. Information includes the cask type deployed, transport license and status as well as
Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life
Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life
Dry cask storage systems are deployed at nuclear power plants for used nuclear fuel (UNF)
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
Dry Cask Storage and Transportation Burnup Credit
Dry Cask Storage and Transportation Burnup Credit
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition (NUREG-75/087)
The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews.
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants: A Guidance Manual for Users of Standard Technical Specifications (NUREG-0133)
This guidance manual provides the NRC staff methodology for calculating parameters for limiting conditions of operation required in the radiological effluent Technical Specifications for light-water-cooled nuclear power plants. it provides guidance in using the model specifications reported in NUREG-0472 (Revision 1)*, and NUREG-0473 (Revision 1)*, applicable to operating PWR and BWR licensees, and users of the Standard Technical Specifications packages available for various vendor designs.
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Recommendations for PWR Storage and Transportation Casks That Use Burnup Credit
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
Regulatory Perspective on Potential Fuel Reconfiguration and Its Implication to High Burnup Spent Fuel Storage and Transportation
The recent experiments conducted by Argonne National Laboratory on high burnup fuel cladding material property show that the ductile to brittle transition temperature of high burnup fuel cladding is dependent on: (1) cladding material, (2) irradiation conditions, and (3) drying-storage histories (stress at maximum temperature) [1]. The experiment results also show that the ductile to brittle temperature increases as the fuel burnup increases.
Issues for Effective Implementation of Burnup Credit
Issues for Effective Implementation of Burnup Credit
In the United States, burnup credit has been used in the criticality safety evaluation for storage pools at
pressurized water reactors (PWRs) and considerable work has been performed to lay the foundation for use of
burnup credit in dry storage and transport cask applications and permanent disposal applications. Many of the
technical issues related to the basic physics phenomena and parameters of importance are similar in each of these
applications. However, the nuclear fuel cycle in the United States has never been fully integrated and the
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan Project Overview Report
As outlined in the overall program for high-level waste (HLW) management in Japan, defined by the Atomic Energy Commission (AEC), HWL separated from spent nuclear fuel during reprocessing will be immobilized in a glass matrix and stored for a period of 30 to 50 years to allow cooling; it will then be disposed of in a stable deep geological formation.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT FOURTH NATIONAL REPORT Argentina
The structure of the Fourth National Report complies with the Guidelines Regarding the
Form and Structure of National Reports (INFCIRC/604/Rev.1).
Section A describes the scope of the nuclear activity developed in Argentina since 1950
as well as the legal and regulatory framework. It also makes reference to the Strategic
Plan for Radioactive Waste Management (Strategic Plan), which refers to the safety of
Spent Fuel Management and Radioactive Waste Management.
Spent Nuclear Fuel Discharges from U.S. Reactors 1994
Spent Nuclear Fuel Discharges from U.S. Reactors 1994
Directory of Certificates of Compliance for Radioactive Materials Packages (NUREG-0383)
Directory of Certificates of Compliance for Radioactive Materials Packages (NUREG-0383)
The purpose of this directory is to make available a convenient source of information on package designs approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packages, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2. The report includes all package designs approved prior to the publication date of the directory as of September 2013.
Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010

Environmental Permitting Guidance Radioactive Substances Regulation For the Environmental Permitting (England and Wales) Regulations 2010
This guidance is aimed at helping readers understand the permitting and other requirements specific to Radioactive Substances Regulation (RSR). The RSR regime covers
- more than one European Directive, parts of which are also implemented by other regulatory regimes which, to an extent, complement RSR;
- various Government policies and strategies; and
The Problem of used nuclear fuel: lessons for interim solutions from a comparative cost analysis
The Problem of used nuclear fuel: lessons for interim solutions from a comparative cost analysis
An acceptable long-term solution for used (spent) fuel from nuclear power reactors has evaded all countries engaged in the civilian
nuclear fuel cycle. Furthermore, many countries are trying to develop interim storage solutions that address the shortage of storage in
the spent fuel cooling pools at reactors. The United States has a particularly acute problem due to its adherence to an open fuel cycle
and its large number of reactors. Two main options are available to address the spent fuel problem: dry storage on-site at reactors and
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Underlying Yucca Mountain: The Interplay of Geology and Policy in Nuclear Waste Disposal
Nuclear waste disposal in the USA is a difficult policy issue infused with
science, technology, and politics. This issue provides an example of the co-production
of scientific knowledge and politics through public policy. The proponents of a
repository site at Yucca Mountain, Nevada, argue that their decision to go ahead
with the site is based on ‘sound science’, but the science they use to uphold their
decision is influenced by politics. In turn, the politics of site selection has been altered
Selection of Away-From-Reactor Facilities for Spent Nuclear Fuel Storage
Selection of Away-From-Reactor Facilities for Spent Nuclear Fuel Storage
With the continuing accumulation of spent fuel at reactor sites, the demand for additional storage of spent fuel at AFR (away from reactor) facilities is growing. It is an issue for most Member States generating nuclear power, including those countries pursuing reprocessing. There are a diversity of technical options and services available which offer competitive, reliable solutions to meet the storage requirements. In particular, dry storage technologies have been widely applied.
Some Principles for Siting Controversial Decisions: Issues from the US Experience with High Level Nuclear Waste
Some Principles for Siting Controversial Decisions: Issues from the US Experience with High Level Nuclear Waste
Beginning with the role of "stakeholders" - those whose interests are, knowingly or unknowingly, affected - in the siting of noxious facilities, this paper seeks to develop principles for acceptable and democratically arrived at polices related to problems associated with advances in and products of science and technology. Although widely regarded as a necessary condition for success, the principles underpinning stakeholder involvement, such as representativeness, are often violated in practice.
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 sporadically over a three-decade period from the late 1950s until 1982, when the U.S. Congress enacted the Nuclear Waste Policy Act (NWPA) codifying 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.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT NATIONAL REPORT ARGENTINA 2003
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT NATIONAL REPORT ARGENTINA 2003
The structure of this National Report complies, to the greatest adjustment possible, with the
Guidelines Regarding the Form and Structure of National Reports approved in the
Preparatory Meeting held in Vienna in December 2001.
Section A includes a general introduction to the report, and a reference to the National
Program which contemplates spent fuel and radioactive waste management and the treatment
of wastes that originate from Mining and Uranium Processing.
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
Dry Cask Storage of Nuclear Spent Fuel
This presentation was given by Earl Easton at the 2011 National State Liaison Officers Conference in Bethesda, MD.
The presentation highlights the current state of spent nuclear fuel as well as the progress toward its ultimate disposal.