原子能科学技术2017，Vol.51Issue(3)：462-467,6.DOI:10.7538/yzk.2017.51.03.0462
氟盐冷却高温堆主冷却剂放射性源项研究
Study on Radioactive Source Term of Primary Coolant System in Fluoride Salt Cooled High Temperature Reactor
摘要
Abstract
T he radioactive source term of primary coolant in fluoride salt cooled high temperature reactor (FHR) was studied in normal operating conditions .The main con-tributions of primary coolant source term were theoretically analyzed .Neutron spec-trum ,fuel source term concentration and source term activation and diffusion in primary coolant were also studied using 3D Monte Carlo transport program KENOⅥ ,burnup analysis program ORIGEN-S and scientific computing program Mathematica .The radio-active source term of primary coolant was quantitatively analyzed based on one kind of design scheme of FHR using this method .The results show that tritium source term in primary coolant is higher than that of other reactors ,tritium production rate is 5.16 ×1014 Bq · GWth-1 · d-1 ,and its release to the environment should be limited using effective method .T he results can be used as reference for engineering design ,radiation protection design ,tritium control and waste treatment system design for FHR .关键词
氟盐冷却高温堆/主冷却剂系统/源项Key words
fluoride salt cooled high temperature reactor/primary coolant system/source term分类
能源科技引用本文复制引用
周波,严睿,邹杨,戴叶,朱贵凤,于世和,刘亚芬,杨璞..氟盐冷却高温堆主冷却剂放射性源项研究[J].原子能科学技术,2017,51(3):462-467,6.基金项目
中国科学院战略性先导研究项目资助(XDA02010200) （XDA02010200）
