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Supplement to the Disposal Criticality Analysis Methodology
Supplement to the Disposal Criticality Analysis Methodology
Screening Analysis of Criticality Features, Events, and Processes for License Application
Screening Analysis of Criticality Features, Events, and Processes for License Application
Technical Evaluation Report on the Content of the U.S. Department of Energy's Yucca Mountain Repository License Application
Technical Evaluation Report on the Content of the U.S. Department of Energy's Yucca Mountain Repository License Application
This “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain License Application; Postclosure Volume: Repository Safety After Permanent Closure” (TER Postclosure Volume) presents information on the NRC staff’s review of DOE’s Safety Analysis Report (SAR), provided on June 3, 2008, as updated by DOE on February 19, 2009. The NRC staff also reviewed information DOE provided in response to NRC staff’s requests for additional information and other information that DOE provided related to the SAR.
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.
Spent Nuclear Fuel Transportation: An Overview
Spent Nuclear Fuel Transportation: An Overview
Spent nuclear fuel comprises a fraction of the hazardous materials packages shipped annually in the United States. In fact, at the present time, fewer than 100 packages of spent nuclear fuel are shipped annually. At the onset of spent fuel shipments to the proposed Yucca Mountain, Nevada, repository, the U.S. Department of Energy (DOE) expects to ship 400 - 500 spent fuel transport casks per year over the life of the facility.
Overview of Vacuum Drying Methods and Factors Affecting the Quantity of Residual Water – Public Version
Overview of Vacuum Drying Methods and Factors Affecting the Quantity of Residual Water – Public Version
NRC initiated a research activity with the Center for Nuclear Waste Regulatory Analyses (CNWRA®) to develop a conceptual test plan for measuring the quantity of residual water remaining in a canister following vacuum drying to the criterion referenced in NUREG–1536. While residual water may be considered as unbound or bound (i.e., physi- or chemisorbed), the focus of this test plan is only the unbound water. This activity consists of the preparation of two technical letter reports. The first is the present report, which describes current industry drying practices and capabilities.
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.