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Integrated Issue Resolution Status Report
Integrated Issue Resolution Status Report
This Integrated Issue Resolution Status Report provides background information about the status of prelicensing interactions between the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) concerning a potential high-level waste geologic repository at Yucca Mountain, Nevada. The NRC staff has, for many years, engaged in prelicensing interactions with DOE and various stakeholders.
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Status of the Joint French ISPN/COGEMA Qualification Programme of Fission Products
Design of Wet Storage Racks for Spent BWR Fuel
Design of Wet Storage Racks for Spent BWR Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
SAS2D--A Two-Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Development and Applications of a Protypic SCALE Control Module for Automated Burnup Credit Analysis
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Use Burnup Credit for Criticality Safety for the Hanford Spent Nuclear Fuel Project
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
Impact of Partially Inserted Control Rods on Actinide-Only Burnup Credit Margin
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
A New Method to Take Burnup into Account in Criticality Studies Considering an Axial Profile of Burn-up Plus some Fission Products
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Experimental Investigation of Burnup Credit for Safe Transport, Storage, and Disposal of Spent Nuclear Fuel
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
A Statistical Method for Estimating the Net Uncertainty in the Prediction of k Based on Isotopic Uncertainties
Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program, Report to the Congress by the Secretary of Energy
Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program, Report to the Congress by the Secretary of Energy
The success of the Civilian Radioactive Waste Management Program of the U.S.
Department of Energy (DOE) is critical to U.S. ability to manage and dispose of
nuclear waste safely--and to the reestablishment of confidence in the nuclear energy
option in the United States. The program must conform with all applicable standards
and, in fact, set the example for a national policy on the safe disposal of radioactive
waste.
The Secretary of Energy has recently completed an extensive review of the
Validation of SCALE-4 for Burnup Credit Applications
Validation of SCALE-4 for Burnup Credit Applications
In the past, criticality analysis of pressurized water reactor (PWR) fuel stored in racks and casks has assumed that the fuel is fresh with the maximum allowable initial enrichment. If credit is allowed for fuel burnup in the design of casks that are used in the transport of spent light water reactor fuel to a repository, the increase in payload can lead to a significant reduction in the cost of transport and a potential reduction in the risk to the public. A portion of the work has been performed at Oak Ridge National Laboratory (ORNL) in support of the U.S.
Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges
Internationalization of the Nuclear Fuel Cycle--Goals, Strategies, and Challenges
The so-called nuclear renaissance has increased worldwide interest in nuclear power.
This potential growth also has increased, in some quarters, concern that nonproliferation
considerations are not being given sufficient attention. In particular, since the introduction of
many new power reactors will lead to requiring an increase in uranium enrichment services to
provide the reactor fuel, the proliferation risk of adding enrichment facilities in countries that do
LINE - Leadership in Nuclear Energy Commission - Full Report
LINE - Leadership in Nuclear Energy Commission - Full Report
Recognizing that Idaho has a major strategic and economic interest in maintaining INL’s leadership role and in helping
the nuclear energy industry successfully meet these broader challenges, Idaho governor C.L. “Butch” Otter established
the Leadership in Nuclear Energy or “LINE” Commission in February 2012.
The Governor recognized that recent national developments in the nuclear energy sector will cause the State of Idaho to
face important choices in the future and that he needed to understand the best options available.
Report to the Secretary of Energy on the Conclusions and Recommendations of the Advisory Panel o Alternative Means of Financing and Managing (AMFM) Radioactive Waste Management Facilities
Report to the Secretary of Energy on the Conclusions and Recommendations of the Advisory Panel o Alternative Means of Financing and Managing (AMFM) Radioactive Waste Management Facilities
The AMFM Panel has submitted its report "Managing Nuclear
Waste - A Better Idea" to the Secretary. The report contains six
general conclusions and one general recommendation in Chapter
XII. In addition, Chapter X contains 14 specific enhancements
("Key Components of Any Waste Management Structure") that are
recommended for implementation by the Office of Civilian Radioactive
Waste Management (OCRWM) or any alternative organization.
This paper lists and discusses the 6 general conclusions, the
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plans, An Historical Analysis
Federal Policy for the Disposal of Highly Radioactive Wastes from Commercial Nuclear Power Plans, An Historical Analysis
How to dispose of highly radioactive wastes from commercial nuclear power plants is a question that has remained unresolved in the face of rapidly changing technological, economic, and political requirements. In the three decades following World War II, two federal agencies--the Atomic Energy Commission and the Energy Research and Development Administration--tried unsuccessfully to develop a satisfactory plan for managing high level wastes.
Consolidated Interim Storage of Commercial Spent Nuclear Fuel-A Technical and Programmatic Assessment
Consolidated Interim Storage of Commercial Spent Nuclear Fuel-A Technical and Programmatic Assessment
Approximately 54,000 tons of spent nuclear fuel are stored at operating nuclear power plants and several decommissioned power plants throughout the country. Spent fuel storage at these sites was never intended to be permanent. The current Federal plan is to place the fuel in a repository for permanent disposal in Nevada at Yucca Mountain.
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.
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
Report on Radioactive Waste Ownership and Management of Long-Term Liabilities in EDRAM Member Countries
This report has been prepared by an ad-hoc Working Group (WG) formed by ANDRA (France), NUMO (Japan), NAGRA (Switzerland) and ENRESA (Spain) in May 2003, after the EDRAM meeting held in Valencia to study the situation in the different EDRAM member countries regarding the treatment of radioactive waste ownership and management of long-term liabilities.