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Bounding criticality safety analyses for shipments of unconfigured spent nuclear fuel
| 题名： | Bounding criticality safety analyses for shipments of unconfigured spent nuclear fuel |
| 作者： | Parks, C.V.;Lichtenwalter, J.J.; |
| 关键词： | 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES;05 NUCLEAR FUELS ; SPENT FUELS; SPENT FUEL CASKS; CRITICALITY; SAFETY ANALYSIS; URANIUM OXIDES U3O8; URANIUM ALLOYS; ALUMINIUM ALLOYS; SILICON ALLOYS; TRANSPORT |
| 摘要： | In November 1996, a request was made to the US 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 US 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-clad U{sub 3}O{sub 8}, UAl{sub x}, and U{sub 3}Si{sub 2} plates, fragments and pieces that had been irradiated at ORNL 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. |
| 总页数： | 7p |
| 报告类型： | 科技报告 |
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