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Shielding Benchmark Calculations of Selected Spent Fuel Storage Cask Experiments

by B. L. Broadhead, Oak Ridge Natl Lab, Oak Ridge, United States,
J. S. Tang, Oak Ridge Natl Lab, Oak Ridge, United States,
C. V. Parks, Oak Ridge Natl Lab, Oak Ridge, United States,
H. Taniuchi, Oak Ridge Natl Lab, Oak Ridge, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1993

Abstract:

This paper describes the application of the three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, to the analysis of a series of benchmark spent fuel storage cask measurements performed at the Idaho National Engineering Laboratory. A total of five storage cask problems were analyzed to determine the expected accuracies of computational analyses using well-established Monte Carlo codes. The results presented herein represent the current status of the work.

Subject Headings: Energy storage | Waste storage | Monte Carlo method | Standards and codes | Radioactive wastes | Nuclear power | Fuels

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