中国氦冷固态实验包层2×6模块中子学计算分析

Neutronics Calculation Analysis for China 2×6 Helium-Cooled Solid Breeder Test Blanket Module

为了满足ITER对波纹度的要求,核工业西南物理研究院提出了新的减少低活化铁素体钢的氦冷固态(HCSB)实验包层模块(TBM)设计方案。采用MCNP程序及ITER全堆MCNP模型,对新设计的2×6HCSB-TBM进行三维中子学计算分析,给出了模块产氚率、核热沉积和功率密度分布等结果。在ITER运行因子为22%时,HCSB-TBM的产氚率为12.68mg/d。TBM内总核热沉积为522.5kW,最高功率密度为11.8W/cm3,出现在氚增殖区Li4SiO4中。计算结果可为TBM进一步的结构、热工水力学优化及其他系统设计提供中子学数据。

In order to meet the requirement of ITER toroidal field ripple effect,a new design of helium-cooled solid breeder test blanket module（HCSB-TBM） with reduced low activation ferritic martensitic stainless steel（LAFM） was proposed by Southwestern Institute of Physics.By using MCNP code and global ITER MCNP model,3D neutronics calculations for the new 2×6 HCSB-TBM design were performed and the results of tritium generation rate,nuclear heating deposit and power density distribution were obtained.The tritium production rate is about 12.68 mg/d while considering ITER duty factor of 22%.The TBM total nuclear heating deposit is about 522.5 kW,and the peak power density is 11.8 W/cm3 which appears in Li4SiO4.The results can provide neutronics data for TBM further structural and thermal-hydraulic optimization and design of other systems.