首页|CFETR先进小样品辐照胶囊优化与热工安全分析

CFETR先进小样品辐照胶囊优化与热工安全分析

Optimization and Thermal Safety Analysis of CFETR Advanced Small Sample Irradiation Capsule

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中国聚变工程试验堆(CFETR)先进材料辐照考验样品所在胶囊结构较为复杂,其内部填充氦气,胶囊肋条尺寸、位置以及胶囊内部填充材料对样品温度影响大.基于STAR-CCM+程序建立CFETR先进小样品辐照装置内胶囊全尺寸模型,针对样品的目标温度,对胶囊的肋条和填充材料进行了调整.对于胶囊内整体样品释热率较低的情况,采用释热率较大的钨材料作为填充材料,可以明显提高整体样品温度;对于局部样品释热率差别较大的情况,调整局部肋条的尺寸和位置,能够很好控制样品间的温度,使样品计算温度满足目标温度范围.结果表明:采用上述方法进行优化后,样品中心温度能够满足目标温度范围,且满足入高通量工程试验堆(HFETR)辐照的热工安全,保证整个辐照任务能够顺利开展.
The capsule structure of the advanced material irradiation test sample in China Fusion Engineering Experimental Reactor(CFETR)is relatively complicated,and the capsule is filled with helium.The size and location of the capsule rib and the material of the filling inside the capsule have great influence on the sample temperature.Based on the STAR-CCM+code,a full-scale capsule model was established in the CFETR advanced small sample irradiation device,and the rib and filler materials of the capsule were adjusted according to the target temperature of the sample.For the problem that the heat release rate of the whole sample in the capsule is low,using tungsten material with higher heat release rate as filling material can significantly increase the overall sample temperature.For the case that the heat release rate of local samples is quite different,the temperature between samples can be well controlled by adjusting the size and position of the local rib,so that the calculated temperature of the sample can meet the target temperature range.The results show that after optimization with the above method,the sample center temperature can meet the target temperature range and meet the thermal safety of irradiation in the High Flux Engineering Test Reactor(HFETR),ensuring the smooth development of the entire irradiation task.

CFETRCapsuleRibFillerOptimizationHFETR

刘畅、刘文斌、戴勇、孙寿华、张平、康长虎、宋霁阳、王凯民、彭蕾、郑鹏飞

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中国核动力研究设计院,成都,610213

瑞士保罗谢尔研究所,瑞士,5303 Villigen

中国科学技术大学,合肥,230026

核工业西南物理研究院,成都,610225

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CFETR 胶囊 肋条 填充物 优化 HFETR

国家磁约束核聚变能发展研究专项

2018YFE0307100

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(2)