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Nuclear Waste: Is There a Need for Federal Interim Storage? Report of the Monitored Retrievable Storage Review Commission
Nuclear Waste: Is There a Need for Federal Interim Storage? Report of the Monitored Retrievable Storage Review Commission
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Radioactive Waste Repositories and Host Regions: Envisaging the Future Together
Environmental Impact Statement Comments, Management of Commercial High-Level and Transuranium-Contaminated Radioactive Waste
Environmental Impact Statement Comments, Management of Commercial High-Level and Transuranium-Contaminated Radioactive Waste
This report summarizes the results of EPA's review of the AEC
draft environmental statement, "Management of Commercial High-Level
and Transuranium-Contaminated Radioactive Waste" (WASH-1539). The
means by which high-level and long-lived radioactive wastes are
managed constitutes one of the most important questions upon which
the public acceptability of nuclear power, with its social and economic
benefits, will be determined. While the generation of power by
nuclear means offers certain benefits from the environmental viewpoint,
Phenomena and Parameters Important to Burnup Credit
Phenomena and Parameters Important to Burnup Credit
Since the mid-1980s, a significant number of studies have been directed at understanding the phenomena and
parameters important to implementation of burnup credit in out-of-reactor applications involving pressurizedwater-
reactor (PWR) spent fuel. The efforts directed at burnup credit involving boiling-water-reactor (BWR)
spent fuel have been more limited. This paper reviews the knowledge and experience gained from work
performed in the United States and other countries in the study of burnup credit. Relevant physics and analysis
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel
This report has been prepared to review relevant background information and provide technical discussion that will help initiate a PIRT (Phenomena Identification and Ranking Tables) process for use of burnup credit in light-water reactor (LWR) spent fuel storage and transport cask applications. The PIRT process will be used by the NRC Office of Nuclear Regulatory Research to help prioritize and guide a coordinated program of research and as a means to obtain input/feedback from industry and other interested parties.
Safety Evaluation Report for Disposal Criticality Analysis Methodology Topical Report, Revision 0
Safety Evaluation Report for Disposal Criticality Analysis Methodology Topical Report, Revision 0
In January 1999, the U.S. Department of Energy (DOE)/Office of Civilian Radioactive
Waste Management (OCRWM) submitted the Disposal Criticality Analysis Methodology
Topical Report, Revision 0 (TR) to the U.S. Nuclear Regulatory Commission (NRC) for
review and approval. The TR presents an overall approach for consideration of postclosure
disposal criticality of commercial and defense high-level waste to be placed at
the proposed Yucca Mountain site. During the course of the review and interactions
Disposal Criticality Analysis Methodology Topical Report
Disposal Criticality Analysis Methodology Topical Report
The fundamental objective of this topical report is to present the planned risk-informed disposal criticality analysis methodology to the NRC to seek acceptance that the principles of the methodology and the planned approach to validating the methodology are sound. The design parameters and environmental assumptions within which the waste forms will reside are currently not fully established and will vary with the detailed waste package design, engineered barrier design, repository design, and repository layout.
Regulations for the Safe Transport of Radioactive Material - 2005 Edition
Regulations for the Safe Transport of Radioactive Material - 2005 Edition
101. These Regulations establish standards of safety which provide an
acceptable level of control of the radiation, criticality and thermal hazards to
persons, property and the environment that are associated with the transport of
radioactive material. These Regulations utilize the principles set forth in both
the “Radiation Protection and the Safety of Radiation Sources”, Safety Series
No. 120 [1] and the “International Basic Safety Standards for Protection
against Ionizing Radiation and for the Safety of Radiation Sources”, Safety
ANSI/ANS-8.27-2008: Burnup Credit for LWR Fuel
ANSI/ANS-8.27-2008: Burnup Credit for LWR Fuel
This standard provides criteria for accounting for reactivity effects of fuel irradiation and radioactive decay in criticality safety control of storage, transportation, and disposal of commercial LWR UO2 fuel assemblies.
This standard assumes the fuel and any fixed burnable absorbers are contained in an intact assembly. Additional considerations could be necessary for fuel assemblies that have been disassembled, consolidated, damaged, or reconfigured in any manner.
Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask
Criticality Analysis of Assembly Misload in a PWR Burnup Credit Cask
The Interim Staff Guidance on burnup credit (ISG-8) for spent fuel in storage and transportation casks, issued by the Nuclear Regulatory Commission’s Spent Fuel Project Office, recommends a burnup measurement for each assembly to confirm the reactor record and compliance with the assembly burnup value used for loading acceptance. This recommendation is intended to prevent unauthorized loading (misloading) of assemblies due to inaccuracies in reactor burnup records and/or improper assembly identification, thereby ensuring that the appropriate subcritical margin is maintained.
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.
Evaluation of a Spent Fuel Repository at Yucca Mountain, Nevada
Evaluation of a Spent Fuel Repository at Yucca Mountain, Nevada
In June 2008, the U.S. Department of Energy (DOE) submitted a license application to the U.S. Nuclear Regulatory Commission (NRC) for the construction of a geologic repository at Yucca Mountain, Nevada, for the disposal of spent nuclear fuel and high-level radioactive waste. The license application was accepted for formal NRC review in September 2008. Throughout the more than 20-year history of the Yucca Mountain project, EPRI has performed independent assessments of key technical and scientific issues to facilitate an understanding of overall repository performance.
Criticality Risks During Transportation of Spent Nuclear Fuel
Criticality Risks During Transportation of Spent Nuclear Fuel
This report presents a best-estimate probabilistic risk assessment (PRA) to quantify the frequency of criticality accidents during railroad transportation of spent nuclear fuel casks. The assessment is of sufficient detail to enable full scrutiny of the model logic and the basis for each quantitative parameter contributing to criticality accident scenario frequencies. The report takes into account the results of a 2007 peer review of the initial version of this probabilistic risk assessment, which was published as EPRI Technical Report 1013449 in December 2006.
An Updated Perspective on the US Nuclear Fuel Cycle
An Updated Perspective on the US Nuclear Fuel Cycle
There has been a resurgence of interest in the possibility of processing the US spent nuclear fuel, instead of burying it in a geologic repository. Accordingly, key topical findings from three relevant EPRI evaluations made in the 1990-1995 timeframe are recapped and updated to accommodate a few developments over the subsequent ten years. Views recently expressed by other US entities are discussed.
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability
Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability
Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability
GAO-15-141: Published: Oct 9, 2014. Publicly Released: Nov 12, 2014.
Evolution Of Repository And Waste Package Designs For Yucca Mountain Disposal System For Spent Nuclear Fuel And High-Level Radioactive Waste
Evolution Of Repository And Waste Package Designs For Yucca Mountain Disposal System For Spent Nuclear Fuel And High-Level Radioactive Waste
STANDARD CONTRACT AMENDMENT FOR NEW REACTORS
STANDARD CONTRACT AMENDMENT FOR NEW REACTORS
The following document is a contract amendment to a standard contract between the United States of America, represented by the U.S. Department of Energy, and a corporation organized and existing under the laws of a given state to dispose of Spent Nuclear Fuel (SNF)and/or High-Level Radioactive Waste (HRW).
Public Participation in Environmental Assessment and Decision Making
Public Participation in Environmental Assessment and Decision Making
The National Research Council established the Panel on Public Participation in Environmental Assessment and Decision Making at the request of U.S. Environmental Protection Agency, the U.S. Department of Energy, and the U.S. Food and Drug Administration, with additional support from the U.S. Forest Service, to assess whether, and under what conditions, public participation achieves the outcomes desired.
Civilian Nuclear Waste Disposal
Civilian Nuclear Waste Disposal
The Congressional Research Service prepared a report in August titled "Civilian Nuclear Waste Disposal." It contains a summary of the radioactive waste management program, and includes an update with recent developments on YM licensing, consent based siting, legislation, volunteer private storage sites, and current policy.
Designing a Process for Selecting a Site for a Deep-Mined, Geologic Repository for High-Level Radioactive Waste and Spent Nuclear Fuel
Designing a Process for Selecting a Site for a Deep-Mined, Geologic Repository for High-Level Radioactive Waste and Spent Nuclear Fuel
If policymakers decide to launch a new repository-siting effort, an understanding of previ¬ous repository-siting efforts, both in the United States and abroad, might help to inform decisions defining and implementing the siting process. For this reason and to apprise the public of a critical issue associated with the long-term management of HLW and SNF, the U.S. Nuclear Waste Technical Review Board has written this report.
Stakeholder Involvement in Decision Making: A Short Guide to Issues, Approaches and Resources
Stakeholder Involvement in Decision Making: A Short Guide to Issues, Approaches and Resources
Radioactive waste management is embedded in broader societal issues such as the
environment, risk management, energy, health policy and sustainability. In all
these fields, there is an increasing demand for public involvement, participation
and engagement. Involvement may take different forms at different phases and
can include sharing information, consulting, dialoguing or deliberating on
decisions with relevant stakeholders. Stakeholder involvement should be seen as a
The Multipurpose Canister Program in Retrospect: Perspective and Issues
The Multipurpose Canister Program in Retrospect: Perspective and Issues
The multipurpose canister (MPC) program represented a major U.S. Department of Energy (DOE) initiative to simplify the management of spent nuclear fuel by enclosing it in a canister acceptable for storage, transport, and disposal. The program was one example of successful interaction between utilities and the DOE. This report documents the history and lessons learned from this substantial effort.
Multipurpose Canister System Design Synopsis Report
Multipurpose Canister System Design Synopsis Report
The multipurpose canister (MPC) concept can simplify the management of spent nuclear fuel by enclosing the fuel permanently in a canister that can be used for long-term dry storage at a utility site, transportation to an interim federal storage facility, and eventual disposal in a repository. This synopsis report summarizes the key design and analysis features of the U.S. Department of Energy (DOE) MPC program.