CFETR堆体活化计算与分析

Activation calculation and analysis for CFETR

运用FLUKA计算程序对中国聚变工程实验堆(CFETR)进行了一维模拟活化运算,得出了产氚包层、屏蔽层、真空室结构材料、环向场线圈等模块的中子活化特性。计算结果表明,在聚变堆以200MW聚变功率持续稳态运行一年后,刚停堆时堆体的总活度为1.05×1019Bq,停堆十年后堆体总活度为1.03×1017Bq,此时堆体的主要残留放射性核素为55Fe。研究结果表明,目前CFETR的设计不存在突出的放射性环境安全问题。

This paper considers the current China fusion engineering test reactor （CFETR） design, and simplifies it to a one-dimensional model. With the multi-particle transport code FLUKA, the neutron activation character of the tritium breeding blanket, shielding layer, vacuum vessel material and TFC of CFETR has been calculated to verify the radiation safety of the present design. The related results provide data reference for designing the components of CFETR and for further neutron activation analysis and calculation. The calculation results show that under the circumstances of one year operation with 200WM fusion power, the total radioactivity is 1.05×10^19Bq after shutdown and 1.03×10^17Bq after cooling for ten years. The primary residual nuclide is 55Fe after decaying for ten years. It shows that there isn’t seriously activation safety issue.