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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
Energy Justice Mapping Tool - Disadvantaged Communities Reporter
Energy Justice Mapping Tool - Disadvantaged Communities Reporter
This tool is intended to allow users to explore and produce reports on census tracts that the U.S. Department of Energy (DOE) has categorized as disadvantaged communities, or DACs, pursuant to Executive Order (EO) 14008 - Tackling the Climate Crisis at Home and Abroad.
3 Reasons Why We Don’t Launch Nuclear Waste into Space
3 Reasons Why We Don’t Launch Nuclear Waste into Space
A viral YouTube video recently discussed the age-old question “why don’t we shoot nuclear waste into space?”
It’s a topic we often get asked about on social media.
While the educational video’s cartoonish depictions of nuclear waste as glowing green ooze made some of our subject matter experts cringe, it’s clear that the content creators did their homework.
Consent-Based Siting Q&A With Dr. Kathryn Huff
Consent-Based Siting Q&A With Dr. Kathryn Huff
Dr. Kathryn Huff, Principal Deputy Assistant Secretary for the Office of Nuclear Energy, explains consent-based siting process and the recently distributed request for information.
Consent-Based Siting: U.S. DOE Climate Action & Spent Nuclear Fuel Management
Consent-Based Siting: U.S. DOE Climate Action & Spent Nuclear Fuel Management
Nuclear energy is essential to tackling climate change. Maintaining the nation’s current fleet and deploying advanced reactors is crucial in achieving the U.S. Department of Energy (DOE)’s ambitious goals of a 50% reduction in carbon emissions by the end of the decade, 100% clean electricity by 2035, and a net-zero economy by 2050.
However, to meet those goals, progress needs to be made in the management of spent nuclear fuel. Inaction on this issue has already cost taxpayers more than $9 billion in settlements and judgments.
Consent-Based Siting: Social Science & Nuclear Waste Management at the U.S. Department of Energy
Consent-Based Siting: Social Science & Nuclear Waste Management at the U.S. Department of Energy
Can anthropologists help the U.S. Department of Energy (DOE) design a more environmentally just, participatory, and consent-based siting process for spent nuclear fuel management facilities? The DOE has committed to a consent-based approach to siting spent nuclear fuel management facilities that aims to enable broad community participation and center equity and environmental justice.
Spending Time on Spent Nuclear Fuel
Spending Time on Spent Nuclear Fuel
Making progress on the long-term management of spent nuclear fuel can be fraught with political and economic challenges, but groups within the U.S. are looking to try and tackle the challenge from many different angles. As the government ramps up efforts to support spent nuclear fuel management up to the limits of the law, ANS and others are making recommendations around, and receiving funding oriented to, pathways for progress.
NRC Online Resources - Storage of Spent Nuclear Fuel Webpage
NRC Online Resources - Storage of Spent Nuclear Fuel Webpage
NRC's "Storage of Spent Nuclear Fuel" includes a short discussion of "What We Regulate"; "How We Regulate"; and links to related information.
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Gateway for Accelerated Innovation in Nuclear (GAIN) Website
Website for Gateway for Accelerated Innovation in Nuclear (GAIN).
The mission of the Department of Energy Office of Nuclear Energy (DOE-NE) is to advance nuclear power as a resource capable of meeting the nation's energy, environmental and national security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development and demonstration ﴾RD&D﴿.
International ENSA/DOE Shock and Vibration Cask Test Video
International ENSA/DOE Shock and Vibration Cask Test Video
This is a video presentation of the ENSA/DOE Multimodal Transportation Test, which began in Spain, crossed the Atlantic Ocean, and progressed by rail to the western US.
Execution Strategy Analysis Conference Papers
Execution Strategy Analysis Conference Papers
Conference papers on the IWM Execution Strategy Analysis process and tool.
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks
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
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.
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.
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
PWR Radiochemical Assay Benchmarks Using SAS2H and CASMO
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.