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Computational Physics and Engineering Division
Bounding Criticality Safety Analyses for Shipments of Unconfigured Spent Nuclear Fuel
| 题名： | Computational Physics and Engineering Division Bounding Criticality Safety Analyses for Shipments of Unconfigured Spent Nuclear Fuel |
| 作者： | J. J. Lichtenwalter and C.V. Parks |
| 关键词： | bounding；division；engineering；clear；critic；onfi；spen；sics；ship；ured |
| 摘要： | In November 1996, a request was made to the U.S. Department of Energy for a waiver for three shipments of spent nuclear fuel (SNF) from Oak Ridge National Laboratory (ORNL) to the Savannah River Site (SRS) in the U.S. NRC certified BMI-1 cask (CoC 5957). Although the post-irradiation fissile mass (based on chemical assays) in each shipment was less than 800 g, a criticality safety analysis' was needed because the pre-irradiation mass exceeded 800 g, the fissile material limit in the CoC. The analyses were performed on SNF consisting of aluminum U3O8, UAl,, and U3Si2 plates, fragments and pieces that had been irradiated at ORI\^ during the Reduced Enrichment Research and Test Reactor Program of the 1980s. The highlights of the approach used to analyze this unique SNF and the benefits of the waiver are presented in this paper. |
| 报告类型： | 科技报告 |
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