中国ITER氦冷固态实验包层模块氚工艺系统设计  

Design of tritium systems for CH HCSB TBM

作　　者：罗德礼[1] 陈长安[1] 黄志勇[1] 刘从贤[1] 熊义富[1] 石岩[1] 雷强华[1] 胡刚[2] 

机构地区：[1]中国工程物理研究院,绵阳621900 [2]核工业西南物理研究院,成都610041

出　　处：《核聚变与等离子体物理》2006年第3期217-222,共6页Nuclear Fusion and Plasma Physics

摘　　要：基于ITERCHHCSBTBM的设计特点,设计了相关的氚工艺辅助系统。描述了氚提取系统(TES)、冷却剂纯化系统(CPS)、氚测量系统(TMS)的功能、设计参数和工艺流程等。TES用于氚提取、储存、同位素的分离;CPS实现氧氮等杂质和氚的去除及冷却剂的定量处理和分析等功能;TMS不仅可以定量分析氚含量,而且必要时可替代TES。氚渗透及氚安全的分析表明,通过CHHCSBTBM以及辅助系统向环境释放的氚可控制在ITER的氚安全限度内。The ancillary tritium systems, including tritium extract system （TES）, coolant purification system （CPS） and tritium measurement system （TMS）, have been designed based on the structure features of Chinese helium cooled solid breeder test blanket module （CH HCSB TBM） for 1TER. Functions, technical parameters, and technological processes of these systems have been described. TES is designed to extract tritium produced in the breeder, to store and separate hydrogen isotope gases. Impurities and tritium in the helium coolant are removed through CPS. TMS has the function of testing the tritium breeding rate in TBM and can replace TES sometimes. Tritium release to the environment from CH HCSB TBM is well controlled below the tritium safety limit of 1TER, according to the tritium permeation and tritium safety analysis.

关 键 词：氚系统设计 CH HCSB TBM 

分 类 号：TL621[核科学技术—核技术及应用]