刘广东,吴维亮,朱贺,马庆俊.事故工况下乏燃料运输容器跌落分析[J].包装工程,2017,38(21):31-34.
LIU Guang-dong,WU Wei-liang,ZHU He,MA Qing-jun.Drop Analysis of the Spent Nuclear Fuel Transport Cask under Accident Conditions[J].Packaging Engineering,2017,38(21):31-34. |
| 事故工况下乏燃料运输容器跌落分析 |
| Drop Analysis of the Spent Nuclear Fuel Transport Cask under Accident Conditions |
| 投稿时间：2017-09-06 修订日期：2017-11-10 |
| DOI： |
| 中文关键词: 乏燃料 运输容器 事故工况 跌落分析 应力校核 |
| 英文关键词: spent nuclear fuel transport cask accident conditions drop analyses stress checking |
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| 中文摘要: |
| 目的 验证乏燃料运输容器本体、内外盖、吊篮和螺栓及其运输包装设计，在事故工况中以最危险角度从9 m高度自由跌落至水平的刚性地面过程中，是否满足GB 11806《放射性物质安全运输规定》的规范要求。方法 采用LS-DYNA进行有限元仿真模拟跌落过程以代替跌落试验，开展乏燃料运输容器9 m自由跌落冲击分析，并根据ASME规范第III卷规定的应力限值对容器本体、内外盖、吊篮和螺栓进行应力校核。结果 应力校核结果显示，乏燃料运输容器本体、内外盖、吊篮和螺栓满足设计强度要求。结论 该乏燃料运输容器本体、内外盖、吊篮和螺栓及其运输包装设计满足GB 11806规范要求。 |
| 英文摘要: |
| The work aims to verify whether the design of the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts as well as its transportation package meets the standard requirements of GB 11806 Regulations for Safe Transport of Radioactive Materials when they are freely dropped to the horizontal rigid ground at the most dangerous angle from the height of 9 m under the accident conditions. The finite element method was utilized to simulate the drop process with LS-DYNA instead of the drop test. The 9 m free drop impact analysis of spent nuclear fuel transport cask was carried out. The stress checking of the cask body, the inner and outer lids, the fuel basket and the bolts was conducted according to the stress limits as specified by ASME. The results of stress checking showed that, the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts met the requirements of design strength. The design of the spent nuclear fuel transport cask body, the inner and outer lids, the fuel basket and the bolts as well as its transportation package satisfies the requirements of GB 11806. |
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