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The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
The Likelihood of Criticality Following Disposal of SF/HLW/HEU/Pu
Letter to President Obama - Blue Ribbon Commission
Letter to President Obama - Blue Ribbon Commission
Dear Mr. President:
At your direction, the Secretary of Energy established the Blue Ribbon Commission on
America’s Nuclear Future to review policies for managing the back end of the nuclear
fuel cycle and recommend a new strategy. We are pleased to be serving as Co‐
Chairmen of the Commission, and we are writing to you to highlight an important action
we strongly believe should be reflected in your Fiscal Year 2013 baseline budget
projections.
In our draft report to the Secretary, issued in July of this year, the Commission
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
Computational Benchmark for Estimated Reactivity Margin from Fission Products and Minor Actinides in BWR Burnup Credit
This report proposes and documents a computational benchmark for the estimation of the
additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor
actinides in a burnup-credit storage/transport environment, relative to SNF compositions
containing only the major actinides. The benchmark problem/configuration is a generic burnupcredit
cask designed to hold 68 boiling water reactor (BWR) spent nuclear fuel assemblies. The
purpose of this computational benchmark is to provide a reference configuration for the
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel
Review and Prioritization of Technical Issues Related to Burnup Credit for BWR Fuel
This report has been prepared to support technical discussion of and planning for future
research supporting implementation of burnup credit for boiling-water reactor (BWR) spent fuel
storage in spent fuel pools and storage and transport cask applications. The review and
discussion in this report are based on knowledge and experience gained from work performed
in the United States and other countries, including experience with burnup credit for
pressurized-water reactor (PWR) spent fuel. Relevant physics and analysis phenomena are
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.
Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety
Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety
Utilization of burnup credit in criticality safety analysis for long-term disposal of spent
nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile
material that will be present in the repository. Burnup-credit calculations are based on depletion
calculations that provide a conservative estimate of spent fuel contents (in terms of criticality
potential), followed by criticality calculations to assess the value of the effective neutron
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel
Nuclide Importance to Criticality Safety, Decay Heating, and Source Terms Related to Transport and Interim Storage of High-Burnup LWR Fuel
This report investigates trends in the radiological decay properties and changes in relative nuclide importance associated with increasing enrichments and burnup for spent LWR fuel as they affect the areas of criticality safety, thermal analysis (decay heat), and shielding analysis of spent fuel transport and storage casks. To facilitate identifying the changes in the spent fuel compositions that most directly impact these application areas, the dominant nuclides in each area have been identified and ranked by importance.
Blue Ribbon Commission on America’s Nuclear Future Draft Report to the Secretary of Energy
Blue Ribbon Commission on America’s Nuclear Future Draft Report to the Secretary of Energy
America’s nuclear waste management program is at an impasse. The Obama Administration’s decision
to halt work on a repository at Yucca Mountain in Nevada is but the latest indicator of a policy that has
been troubled for decades and has now all but completely broken down. The approach laid out under
the 1987 Amendments to the Nuclear Waste Policy Act (NWPA)—which tied the entire U.S. high-level
waste management program to the fate of the Yucca Mountain site—has not worked to produce a
Reactor and Fuel Cycle Technology Subcommittee Report to the Full Commission Updated Report
Reactor and Fuel Cycle Technology Subcommittee Report to the Full Commission Updated Report
The Reactor and Fuel Cycle Technology Subcommittee was formed to respond to the charge—set forth in the charter of the BRC—to evaluate existing fuel cycle technologies and R&D programs in terms of multiple criteria.
Enhancing the Role of State and Local Governments in America’s Nuclear Future: An Idea Whose Time Has Come
Enhancing the Role of State and Local Governments in America’s Nuclear Future: An Idea Whose Time Has Come
This paper, prepared to aid the Blue Ribbon Commission on America’s Nuclear Future in its
deliberations, includes a discussion of the issues that would be faced in the siting, permitting and
licensing of storage and disposal facilities for the “back end” of the commercial nuclear fuel
cycle and for the Department of Energy’s (DOE) high–level radioactive waste. It discusses the
authority that could be employed by non–federal levels of government in supporting or opposing
Blue Ribbon Commission on America’s Nuclear Future Report to the Secretary of Energy
Blue Ribbon Commission on America’s Nuclear Future Report to the Secretary of Energy
This report highlights the findings and conclusions of the Blue Ribbon Commission on America’s Nuclear Future (BRC) and presents recommendations for consideration by the Administration and Congress, as well as interested state, tribal and local governments, other stakeholders, and the public.
Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository, Volume II: Immobilized In Ceramic
Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository, Volume II: Immobilized In Ceramic
As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix.