高放废物核心处置单元传热数值模拟研究OA
Numerical simulation on heat transfer in core disposal element of high-level radioactive waste
高放废物核心处置单元传热机理对于缓冲材料设计及处置概念设计有着重要的工程意义.以核心处置单元为研究对象,构建了相应传热数值模型,采用数值模拟软件COMSOL Multiphysics,开展了缝隙宽度及缝隙内颗粒填充对处置单元传热影响的数值模拟研究.研究结果表明,当外缝隙为50 mm,内缝隙分别为15、10和5 mm时,缓冲材料最高温度分别为363.4、363.16 和362.91 K,改变缝隙宽度对缓冲材料最高温度影响不显著.当外缝隙为50 mm,内缝隙为10 mm,内缝隙填充或者不填充颗粒时,缓冲材料的最高温度分别为363.16和366.1 K,处置单元内缝隙填充颗粒时可更好地传导玻璃固化体所释放的热量.外缝隙宽度为50 mm,内缝隙宽度分别为15、10和5 mm,内缝隙不填充颗粒,此时缓冲材料最高温度分别为366.95、366.1和364.73 K,当废物罐与缓冲材料之间不得不预留缝隙时,缝隙的宽度越小,越有利于玻璃固化体释放的热量向外传导.
It is of significant engineering importance to study the heat transfer mechanism in the core disposal element of high-level radioactive waste(HLW),especially for the design of buffer material and the overall disposal concept.In this paper,the core disposal element was taken as the research object,and a corresponding numerical model for heat transfer was established.This study employed the numerical simulation software COMSOL Multiphysics to investigate the effects of gap width and gap filling with buffer granules on the heat transfer performance of the disposal element.The results indicated that when the width of outer gap was 50 mm and the inner gap was 15,10,and 5 mm,respectively,the maximum temperatures of the buffer material were 363.4,363.16 and 362.91 K,respectively.Varying the gap width has no significant effect on the maximum temperature of the buffer material.When the width ofouter gap was 50 mm and the width ofinner gap was 10 mm,the maximum temperatures of the buffer material were 363.16 and 366.1 K for the cases with and without buffer granular filling in the inner gap,respectively.The presence of granular filling in the inner gap of the disposal element enhanced the heat transfer from the vitrified waste to the surrounding granite.When the width of outer gap was fixed at 50 mm and the width of inner gap measured 15 mm,10 mm,and 5 mm respectively,without buffer granular filling,the maximum temperatures of the buffer material were 366.95,366.1 and 364.73 K.This indicates that if a gap between the canister and the buffer material is unavoidable,a smaller gap width is more favorable for the outward conduction of heat released by the vitrified waste.
张奇;谢敬礼;曹胜飞;成建峰
核工业北京地质研究院,北京 100029||中国国家原子能机构高放废物地质处置创新中心,北京 100029核工业北京地质研究院,北京 100029||中国国家原子能机构高放废物地质处置创新中心,北京 100029核工业北京地质研究院,北京 100029||中国国家原子能机构高放废物地质处置创新中心,北京 100029核工业北京地质研究院,北京 100029||中国国家原子能机构高放废物地质处置创新中心,北京 100029
能源科技
高放废物地质处置缓冲材料高庙子膨润土传热热辐射
geological disposal of high-level radioactive wastebuffer materialGaomiaozi bentoniteheat transferthermal radiation
《世界核地质科学》 2026 (2)
345-355,11
国家原子能机构核设施退役及放射性废物治理项目资助 Supported by China Atomic Energy Authority(CAEA)through the Geological Disposal Program
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