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Interim Storage, Environmental Justice, and Generational Equity

Interim Storage, Environmental Justice, and Generational Equity

Author(s)
Leigh, C.D. ,
Dotson, L.J.
Publication Date

With the termination of the Yucca Mountain project, which was proposed to be our nation’s first repository for the disposal of military and civilian spent nuclear fuel and high-level radioactive waste, the future of nuclear waste management and disposal in this country became increasingly uncertain. Interim storage has been advocated by many as a temporary solution while a permanent solution is studied for potentially several more decades to come.

Interim Storage, Environmental Justice, and Generational Equity

Interim Storage, Environmental Justice, and Generational Equity

Author(s)
Leigh, C.D. ,
Dotson, L.J.
Publication Date

With the termination of the Yucca Mountain project, which was proposed to be our nation’s first repository for the disposal of military and civilian spent nuclear fuel and high-level radioactive waste, the future of nuclear waste management and disposal in this country became increasingly uncertain. Interim storage has been advocated by many as a temporary solution while a permanent solution is studied for potentially several more decades to come.

Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts

Environmental Risk Characterization Work Plan Yankee Nuclear Power Station Rowe, Massachusetts

Author(s)
Gradient Corporation
Publication Date
This document presents a work plan for performing an environmental risk assessment to support the environmental site closure underway at the Yankee Nuclear Power Station (YNPS). A work plan for the human health risk assessment was submitted as a separate document (Gradient, 2006). The YNPS is located in the town of Rowe, situated in northwestern Massachusetts along the Deerfield River adjacent to Sherman Dam (Figure 1-1).
ynps enviornmental risk characterization work plan

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

EQ6 Calculations for Chemical Degradation of PWR LEU and PWR MOX Spent Fuel Waste Packages

Author(s)
Paul L. Cloke
Publication Date
The Monitored Geologic Repository (MGR) Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating (CRWMS M&O) contractor performed calculations to provide input to the design of a waste package (WP). This document analyzes the degradation processes of two types of pressurized water reactor (PWR) spent nuclear fuel (SNF): • Fuel fabricated from low enriched uranium oxide, which has been used, or will ~ used, in commercial nuclear power plants.
criticality low-enriched uranium monitored geologic repository storage mox fuel waste package degradation pwr snf corrosion plutonium oxide geochemical analysis bba000000-01717-0210-00009 uranium oxide

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

Author(s)
Mueller, D. E. ,
Wagner, J. C.
Publication Date
The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.
burnup credit criticality analysis iaea-tecdoc-1547 iaea sensitivity analysis

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

OECD/NEA Burnup Credit Criticality Benchmark, Analysis of Phase II-B Results: Conceptual PWR Spent Fuel Transportation Cask

Author(s)
Nouri, A.
Publication Date
The OECD/NEA “Burn-up Credit Criticality Benchmark” working group has studied the effect of axial burn-up profile on the criticality of a realistic PWR spent fuel transport cask (Phase II-B). The final results of this benchmark are presented and analysed in this report. Nine basic cases and two additional accident configurations were considered with the following varying parameters: burn-up (0 GWd/t for fresh fuel, 30 and 50 GWd/t), fuel composition (actinides only and actinides with fifteen fission products), axial burn-up discretisation (1 or 9 zones).
criticality pwr fuel transport cask end effect source convergence burnup axial burnup profile

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

Author(s)
Parks, C. V. ,
Gauld, I. C. ,
Wagner, J. C. ,
Broadhead, B. L. ,
DeHart, M. D. ,
Ebert, D. D.
Publication Date
The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities. The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).
burnup credit transport cask storage cask criticality safety analysis

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 3-Surry Unit 1 Cycle 2

Author(s)
Hermann, O. W. ,
Bowman, S. M.
Publication Date
The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit for the negative reactivity of the depleted (or spent) fuel isotopics is desired, it is necessary to benchmark computational methods against spent fuel critical configurations.
burnup credit scale pwr ornl/tm-12294/v3 surry
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