摘要
根据IAEA安全标准No.6有关规程的要求,采用工程传热学和工程力学分析方法,对未经国标GB1180689规定试验的钴60源运输容器的安全性作了分析。经计算分析得,本容器外表面辐射水平为1.56mSvh-1,小于IAEA有关规程规定的2mSvh-1限值。容器经改进后,在800℃火焰中曝射30分钟,其铅温度为166.4℃,小于IAEA有关规程规定的200℃限值。本容器与国内工业用钴60源运输容器相比,具有承受正常运输和事故运输条件的能力,其货包的安全性符合GB1180689和IAEA的规定要求。
Analysis method of engineering heat transfer and engineering mechanics has been used to confirm safety proterties of transporting container for 60Co source that has not been carried out tests provide for by national standard GB11806 89 according demands of IAEA safety standard No.6(brifly called IAEA“REGULATION”).Analyses and computation show that radiation level on surface from container is 1.56mSv·h-1.The value is less than 2mSv·h-1 standard value provide for by IAEA“REGULATION”.The container improved is fired at 800℃ dupeltion 30min.Temperature of Pb is 166.4℃,and littlely lower than 200℃ limited value of IAEA“REGULATION”.The container has capability of free condition and accdient condition for transportation.The safety proterties of loading accord with the demands of GB11806 89 and IAEA“REGULATION”.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1997年第1期91-96,共6页
Nuclear Power Engineering
关键词
钴60源
运输容器
安全分析
Co source Transporting container Safe analyses