摘要
模块式高温气冷堆MHTGR(简称模块堆)一回路冷却剂氦气中放射性核素浓度的计算是辐射防护设计和环境影响评价的基础。本文根据模块堆一回路氦气中放射性核素的来源和去除机制导出了氦气中放射性核素浓度的计算方法,并得出解析解的计算公式。
The calculation on radionuclide concentration in the helium of primary loopfor the module high temperature gas --cooled reactor (MHTGR) is the basis of radiationprotection design and environment impact assessment. Based on the original and removal mechanisms of radionuclides in the helium of primary loop of the module reactor,the calculation models on radionuclide concentration in the helium are derived and thecalculation formulas are given.
出处
《清华大学学报(自然科学版)》
EI
CAS
CSCD
北大核心
1994年第3期101-107,共7页
Journal of Tsinghua University(Science and Technology)
关键词
高温
气冷型堆
氦气
放射性同位素
high temperature gas - cooled reactor
calculation method
radioactivity