新燃料元件运输容器热工安全分析及试验验证  

Thermal Safety Analysis and Experimental Validation of New Fuel Element Transportation Container

作　　者：郭春秋[1] 邹佳讯 衣大勇[1] 张金山[1] GUO Chun-qiu ZOU Jia-xun YI Da-yong ZHANG Jin-shan(China Institute of Atomic Energy, P. O. Box 275-33, Beijing 102413, China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413

出　　处：《原子能科学技术》2016年第11期1992-1997,共6页Atomic Energy Science and Technology

摘　　要：新燃料元件运输容器是为运输493反应堆燃料元件设计的专用设备。为保证燃料元件在运输过程中的安全性,使运输容器及燃料元件的各项性能指标符合标准GB 11806—2004的要求,对运输容器进行了热工设计计算和验证试验。通过计算与相应热工试验结果的比较,验证了运输容器热工设计的准确性。采用该运输容器运输新燃料元件,在正常运输工况和事故运输工况下可保证燃料元件的安全,完全满足GB 11806—2004的规定。The new fuel element transportation container is a specific equipment designed for transporting 493reactor＇s fuel elements.In order to insure the safety of fuel elements during transportation and fulfill the requirements of standard GB 11806—2004,thermal design calculation and validation experiments were carried out.The accuracy of the container＇s thermal design was proven by comparing thermal design results with thermal experimental data.The safety of the new fuel elements can be insured and the requirements of GB 11806—2004can be fulfilled by using the new fuel elements transportation container under both normal transport condition and accidental transport condition.

关 键 词：运输容器 热工设计 验证试验 正常运输工况 事故运输工况 

分 类 号：TL33[核科学技术—核技术及应用]