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Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Research Supporting Implementation of Burnup Credit in Transport and Storage Casks
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Comparison of Computational Estimations of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Impact of Integral Burnable Absorbers on PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
Spent Fuel Criticality Benchmark Experiments
Spent Fuel Criticality Benchmark Experiments
The Burn-Up Credit Experimental Programme REBUS
The Burn-Up Credit Experimental Programme REBUS
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Addressing the Axial Burnup Distribution in PWR Burnup Credit Criticality Safety
Reactivity End-Effects Estimates Using a K Perturbation Model
Reactivity End-Effects Estimates Using a K Perturbation Model
Criticality Safety Evaluation of Fuel Storage Pools in Spain
Criticality Safety Evaluation of Fuel Storage Pools in Spain
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
A Validated Methodology for Evaluating Burnup Credit in Spent Fuel Casks
Characterization of Spent Fuel Approved Testing Material - ATM-104
Characterization of Spent Fuel Approved Testing Material - ATM-104
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Uncertainties in Criticality Analysis Which Affect the Storage and Transportation of LWR Fuel
Characterization of Spent Fuel Approved Testing Material - ATM 103
Characterization of Spent Fuel Approved Testing Material - ATM 103
Characterization of Spent Fuel Approved Testing Material
Characterization of Spent Fuel Approved Testing Material
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Reactivity and Isotopic Composition of Spent PWR Fuel as a Function of Initial Enrichment, Burnup, and Cooling Time
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Feasibility and Incentives for the Consideration of Spent Fuel Operating Histories in the Criticality Analysis of Spent Fuel Shipping Casks
Analyses have been completed that indicate the consideration of spent fuel histories (''burnup credit'') in the design of spent fuel shipping casks is a justifiable concept that would result in cost savings and public risk benefits in the transport of spent nuclear fuel. Since cask capacities could be increased over those of casks without burnup credit, the number of shipments necessary to transport a given amount of fuel could be reduced.
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
Characterization of LWR Spent Fuel MCC-Approved Testing Material--ATM-101
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Generic Reactivity Equivalence of PWR Fuel in Spent Fuel Storage Racks
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Conservative Axial Burnup Distributions for Actinide-Only Burnup Credit
Reversibility and Retrievability in Planning for Geological Disposal of Radioactive Waste-Proceedings of the "R&R" International Conference and Dialogue, December 14-17, 2010, Reims, France
Reversibility and Retrievability in Planning for Geological Disposal of Radioactive Waste-Proceedings of the "R&R" International Conference and Dialogue, December 14-17, 2010, Reims, France
In 2007 the OECD Nuclear Energy Agency (NEA) Radioactive Waste Management Committee
(RWMC) launched a four-year project on the topics of reversibility and retrievability in geological
disposal. The goal of the project studies and activities (www.oecd-nea.org/rwm/rr) was to
acknowledge the range of approaches to reversibility and retrievability (R&R), rather than to
recommend a specific approach, and to provide a basis for reflection rather than to lead towards
Draft Global Nuclear Energy Partnership Programmatic Environmental Impact Statement
Draft Global Nuclear Energy Partnership Programmatic Environmental Impact Statement
This Programmatic Environmental Impact Statement (PEIS) provides an analysis of the potential environmental impacts of the proposed Global Nuclear Energy Partnership (GNEP) program, which is a United States (U.S.) Department of Energy (DOE) program intended to support a safe,
secure, and sustainable expansion of nuclear energy, both domestically and internationally. Domestically, the GNEP Program would promote technologies that support economic, sustained production of nuclear-generated electricity, while reducing the impacts associated with
CRS Report for Congress, Civilian Nuclear Spent Fuel Temporary Storage Options
CRS Report for Congress, Civilian Nuclear Spent Fuel Temporary Storage Options
The Department of Energy (DOE) is studying a site at Yucca Mountain, Nevada, for a
permanent underground repository for highly radioactive spent fuel from nuclear reactors,
but delays have pushed back the facility’s opening date to 2010 at the earliest. In the
meantime, spent fuel is accumulating at U.S. nuclear plant sites at the rate of about 2,000
metric tons per year. Major options for managing those growing quantities of nuclear spent
fuel include continued storage at reactors, construction of a DOE interim storage site near
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Partnering for Long-term Management of Radioactive Waste-Evolution and Current Practice in Thirteen Countries
Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery
Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery
Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima
Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three
Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be
drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery
effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: