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

针对氟盐冷却高温堆(FHR)正常运行时主冷却剂放射性源项进行了研究。对主回路源项主要贡献来源及产生原理进行了分析,基于三维蒙特卡罗输运程序KENOⅥ、燃耗分析模块ORIGEN-S及Mathematica程序,对堆芯中子能谱、堆芯源项及主回路源项扩散及活化进行了分析。应用该方法对FHR的一种设计堆型进行了定量分析,结果表明:主回路氚源项相对其他堆的较高,其产生率为5.16×1014 Bq·GWth^(-1)·d^(-1),应采取有效措施限制其向环境的释放。本文结果可为FHR的工程设计、辐射防护设计、氚源项控制、三废处理系统设计等提供参考。

The 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 313 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 is5.16×1014 Bq·GWth-1·d-1, and its release to the environment should be limited using effective method. The results can be used as reference for engineering design, radiation protection design, tritium control and waste treatment system design for FHR.