Thermal Design and Verification of a Transport Container for Co-60 Waste Source

Dajie Zhuang, Guoqiang Li, Hongchao Sun, Xuexin Wang
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Abstract

The thermal protection performance of the transport container should be considered when designing the radioactive waste source transport container with higher decay heat. The temperature distribution of the container under the normal conditions of transport for heat transfer performance and accident conditions for thermal performance are analyzed and calculated using the finite element analysis method, and the verification test is carried out. Both analysis and test results show that under normal conditions, the container can export the decay heat from the radiation source, and the container can be used in a non-exclusive manner for an accessible surface temperature of less than 50°C. Moreover, under accident conditions, it can effectively prevent the external heat from the fire environment so that the temperature of shielding parts of the container is lower than 327°C, which is the melting point of lead, and ensure the shielding performance is not lost. Its thermal performance meets the relevant requirements of standards and design.
Co-60废弃物源运输容器的热设计与验证
在设计衰变热较高的放射性废物源运输容器时,应考虑运输容器的热防护性能。采用有限元分析方法对集装箱在正常运输条件下的换热性能和事故条件下的温度分布进行了分析计算,并进行了验证试验。分析和试验结果均表明,在正常条件下,该容器可以将辐射源的衰变热输出,并且该容器可以在小于50℃的可达表面温度下以非独占方式使用。而且,在事故条件下,它可以有效地防止来自火灾环境的外部热量,使容器屏蔽部件的温度低于铅的熔点327℃,确保屏蔽性能不丧失。其热工性能满足标准和设计的相关要求。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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