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An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Isotopic Composition Predictions
Taking credit for the reduced reactivity of spent nuclear fuel in criticality analyses is referred to
as burnup credit. Criticality safety evaluations employing burnup credit require validation of the
depletion and criticality calculation methods and computer codes with available measurement
data. To address the issues of burnup credit criticality validation, the U.S. Nuclear Regulatory
Commission initiated a project with Oak Ridge National Laboratory to (1) develop and establish
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity Coefficient Generation for a Burnup Credit Cask Model Using TSUNAMI-3D
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
This paper provides insights into the neutronic similarities between a representative high-capacity rail-transport cask containing typical pressurized water reactor (PWR) spent nuclear fuel assemblies and critical reactor state-points, referred to as commercial reactor critical (CRC) state-points. Forty CRC state-points from five PWRs were analyzed, and the characteristics of CRC state-points that may be applicable for validation of burnup-credit criticality safety calculations for spent fuel transport/storage/disposal systems were identified.
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit
The purpose of this study is to provide insights into the neutronic similarities that may exist between a
generic cask containing typical spent nuclear fuel assemblies and commercial reactor critical (CRC) state-
points. Forty CRC state-points from five pressurized-water reactors were selected for the study and the
type of CRC state-points that may be applicable for validation of burnup credit criticality safety
calculations for spent fuel transport/storage/disposal systems are identified. The study employed cross-
Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages
Sensitivity and Parametric Evaluations of Significant Aspects of Burnup Credit for PWR Spent Fuel Packages
Spent fuel transportation and storage cask designs based on a burnup credit approach must
consider issues that are not relevant in casks designed under a fresh-fuel loading assumption. For
example, the spent fuel composition must be adequately characterized and the criticality analysis
model can be complicated by the need to consider axial burnup variations. Parametric analyses are
needed to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions
Taking credit for the reduced reactivity of spent nuclear fuel (SNF) in criticality analyses is referred to as burnup credit (BUC). Criticality safety evaluations require validation of the computational methods with critical experiments that are as similar as possible to the safety analysis models, and for which the keff values are known. This poses a challenge for validation of BUC criticality analyses, as critical experiments with actinide and fission product (FP)
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
Making Nuclear Waste Governable: Deep Underground Disposal and the Challenge of Reversibility
This book is the result of a collaboration that began over two years ago between researchers from the social sciences and Andra engineers and natural scientists. Contributions to the various chapters have been discussed and enhanced, especially during the workshop and the interdisciplinary conference both held by Andra in 2008 and 2009<br>respectively.
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
Possible Strategies for Geoscientific Classification for High-Level Waste Repository Site Selection
This work was performed to suggest possible strategies for geoscientific classifications in the siting process of a high-level repository. To develop a feasible method for geoscientific classifications, a number of factors of a philosophical character, related to the purpose of the classifications, need to be accounted for. Many different approaches can be visualized, and this report was not intended to present a complete classification methodology.
Geological Disposal of Higher Activity Radioactive Wastes
Geological Disposal of Higher Activity Radioactive Wastes
This is one of three CoRWM reports to Government in 2009. The reports are about: <br><br>_ interim storage of higher activity wastes (including waste conditioning, packaging and transport, and the management of materials that may be declared to be wastes) <br>_ the implementation of geological disposal of higher activity wastes (this report) <br>_ research and development for interim storage and geological disposal. <br><br>The reports cover the three strands of the Government_s Managing Radioactive Waste Safely programme.
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
Managing our Radioactive Waste Safely: CoRWM's recommendations to Government
The Committee on Radioactive Waste Management was asked by Government in 2003 to make recommendations for the long-term management of the UK’s higher activity wastes that would both protect the public and the environment, and inspire public confidence. To do this, we have combined a technical assessment of options with ethical considerations, examination of overseas experience and a wide-ranging programme of engagement both with the public and with interested parties (stakeholders). I am happy to present our recommendations in the pages that follow.
Committee on Radioactive Waste Management Seventh Annual Report
Committee on Radioactive Waste Management Seventh Annual Report
This is the seventh CoRWM Annual Report. It summarises the outcomes of CoRWM’s scrutiny and advice work during the year. It also contains the Committee’s views on the current status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK. All the Committee Members have contributed to this Report and I am grateful to Marion Hill and the Secretariat for all their hard work in compiling it.
Committee on Radioactive Waste Management Eighth Annual Report
Committee on Radioactive Waste Management Eighth Annual Report
This is the eighth CoRWM Annual Report. It summarises CoRWM’s scrutiny and advice for the financial year ending on 31 March 2012. It also contains the Committee’s views on the status of arrangements and plans for the long-term management of higher activity radioactive wastes in the UK at June 2012.
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
ASSESSMENT OF THE GENERIC DISPOSAL SYSTEM SAFETY CASE for Information
The Committee on Radioactive Waste Management (CoRWM) has carried out an assessment of the generic Disposal System Safety Case (gDSSC) published by the Radioactive Waste Management Directorate (RWMD) of the Nuclear Decommissioning Authority (NDA) in February 2011. The assessment covered the whole suite of gDSSC documents, and related RWMD reports on research and development (R&D) and site characterisation.
Additional Media Studies for Site Suitability Criteria
Additional Media Studies for Site Suitability Criteria
Site suitability studies at LLL to date have considered repositories in bedded salt and shale.
NRC Comments on DOE Draft Environmental Assessment for the Deaf Smith County Site
NRC Comments on DOE Draft Environmental Assessment for the Deaf Smith County Site
Nuclear-Waste Disposal in Geologic Repositories
Nuclear-Waste Disposal in Geologic Repositories
Deep geologic repositories are being widely studied as the most favored method of disposal of nuclear waste. Scientists search for repository sites in salt, basalt, tuff and granite that are geologically and hydrologically suitable. The systematic evaluation of the safety and reliability of deep geologic disposal centers around the concept of interacting multiple barriers. The simplest element to describe of the geologic barrier is the physical isolation of the waste in a remote region at some depth within the rock unit.
U.S. DEPARTMENT OF ENERGY’S SITING GUIDELINES AT 10 CFR 963
U.S. DEPARTMENT OF ENERGY’S SITING GUIDELINES AT 10 CFR 963
The U.S. Department of Energy (DOE) has amended the policies under the Nuclear Waste Policy Act of 1982 for evaluating the suitability of Yucca Mountain, Nevada, as a site for development of a nuclear waste repository. The final rule at Title 10, Part 963 of the Code of Federal Regulations (10 CFR Part 963) focuses on the criteria and methodology to be used for evaluating relevant geological and other related aspects of the Yucca Mountain site.
Geological Challenges in Radioactive Waste Isolation
Geological Challenges in Radioactive Waste Isolation
Over the past forty years, the development of the technology needed to isolate radioactive waste in underground rock systems has been found to be a formidable problem. This is especially the case in connection with high-level waste (HLW) after its removal from operations in nuclear power plants. There is also the additional problem of isolating low- and intermediate-level waste (LILW).
Measures of Geologic Isolation
Measures of Geologic Isolation
Isolation in a geologic setting has been the generally favored solution to the high-level radioactive waste (HLW) problem since a scientific basis for nuclear waste management began to be formulated over half a century ago. Although general features of suitable settings have been enumerated, quantitative measures of the safety of geologic isolation of HLW are challenging to devise and to implement.
Review of the U.S. Department of Energy's National Survey of Crystalline Rocks
Review of the U.S. Department of Energy's National Survey of Crystalline Rocks
Location Performance Objectives for the NNWSI Area-to-Location Screening Activity
Location Performance Objectives for the NNWSI Area-to-Location Screening Activity
Fifty-four objectives were identified to guide the screening of the Nevada Research and Development Area of the Nevada Test Site for relatively favorable locations for the disposal of nuclear waste in a mined geologic repository. The objectives were organized as a hierarchy composed of 4 upper-level, 12 middle-level, and 38 lower-level objectives. The four upper-level objectives account for broad national goals to contain and isolate nuclear waste in an environmentally sound and economically acceptable manner.