摘要
运用聚变堆放射性计算程序FDKR和衰变链数据库AFDC-DLIB,计算了ITER中国氦冷固态增殖试验包层模块设计中活化产物的放射性、衰变余热和潜在生物危害因子BHP值。计算结果表明:对于试验包层模块来说,在500MW聚变功率下运行一年,停堆时的总放射性、余热和BHP值分别为2.10×1016Bq、5.06×10-3MW和68.6km3.(kW)-1。结果表明:中国氦冷实验包层模块不存在突出的安全问题。
With an activation calculation code FDKR and decay chain data library AF-DCDLIB, the radioactivity, decay afterheat and biological hazard potential (BHP) from activation products in ITER China helium coolant solid breeder test klanket modular have been calculatd. The calculation results show that the total radioactivity inventory, decay heat and BHP are 2.10 × 10^16 Bq, 5.06× 10^- 3 MW, 68.6km^3 · (kW)^ - 1, respectively, at shutdown after one year operation with 500 MW fusion power. It shows that there isn't seriously environmental safety issue.
出处
《核聚变与等离子体物理》
EI
CAS
CSCD
北大核心
2005年第3期183-188,共6页
Nuclear Fusion and Plasma Physics
基金
国家自然科学基金资助项目(10275017)
关键词
实验包层
活化
衰变余热
潜在生物危害因子
环境安全
TBM
Activity
Decay afterheat
Biological hazard potential (BHP)
Environmental safety