Strength Analysis for Equipment Gate of Nuclear Power Plants
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摘要: 在核电厂运行期间和事故状态下,设备闸门处于关闭状态,与反应堆安全壳一起组成第三层屏蔽,防止放射性物质外泄,是安全壳压力边界的重要组成部分。本文基于ANSYS有限元分析方法和法国《压水堆核电厂机械设备设计和建造规则》(RCC-M)规范理论,对核电厂设备闸门及其支架部件进行了详细应力计算分析,计算分析结果满足RCC-M规范要求。该方法分析全面、正确合理,通过国家核安全局审查。Abstract: In the operation condition and accident condition,the equipment gate in the nuclear power plants is closed and acts as the third shielding together with the reactor containment,to prevent the release of radioactive materials,and so it is one important part of containment pressure boundary.Based on the FEA method of ANSYS and RCC-M normative theory,a detailed stress calculation analysis is conducted for the equipment gate and its support components in nuclear power plants,and the result is in accordance with the RCC-M rule.The analysis method is reasonable and accepted by NNSA.
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Key words:
- Equipment gate /
- ANSYS /
- RCC-M /
- Structure strength
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