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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

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel: 2022 Update

Author(s)
U.S. Nuclear Waste Technical Review Board
Publication Date

In October 2009, the U.S. Nuclear Waste Technical Review Board (Board or NWTRB) published Survey of National Programs for Managing High-Level Radioactive Waste and Spent Nuclear Fuel.  For each of the 13 national programs studied, the report catalogued 15 institutional arrangements that had been set in place and 15 technical approaches that had been taken to design repository systems for the long-term management of high-activity radioactive waste.

Gateway for Accelerated Innovation in Nuclear (GAIN) Website

Gateway for Accelerated Innovation in Nuclear (GAIN) Website

Author(s)
Gateway for Accelerated Innovation in Nuclear
Publication Date

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﴿.

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