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Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments

Authors :
Jabo S. Tang
Hiroaki Taniuchi
Cecil V. Parks
B.L. Broadhead
Robert L. Childs
Source :
Nuclear Technology. 117:206-222
Publication Year :
1997
Publisher :
Informa UK Limited, 1997.

Abstract

The three-dimensional Monte Carlo code MORSE-SGC, as implemented in the SCALE system calculational sequence SAS4, is applied to the analysis of a series of simple geometry benchmark experiments and prototypic spent-fuel storage cask measurements. The simple geometry experiments were performed in Japan and at the General Electric-Morris Operation facility; the cask measurements were performed at the Idaho National Engineering Laboratory. The quantification of uncertainties in a typical shielding analysis process for transport/storage casks can be accomplished by comparison of consistent trends between calculated and measured dose rate quantities in both benchmark and prototypic environments. Benchmark results typically measure the validity of cross-section data and computer code adequacy; prototypic environments, however, generally measure the overall validity of the calculational procedure. A total of five storage cask problems and two simple geometry problems were analyzed to determine the expected accur...

Details

ISSN :
19437471 and 00295450
Volume :
117
Database :
OpenAIRE
Journal :
Nuclear Technology
Accession number :
edsair.doi...........8a6d0a9a11d87ca8dcc2de0b01e4e2ec
Full Text :
https://doi.org/10.13182/nt97-a35326