CFETR第一壁及赤道面外包层中子辐照损伤初步分析

摘要

Background:Chinese Fusion Engineering Testing Reactor (CFETR) is an International Thermonuclear Experimental Reactor (ITER)-like test superconducting tokamak fusion reactor to bridge the gap between ITER and future fusion power plant. The first wall (FW) of blanket and divertor faces the plasma core directly, and the radiation damage of the FWs is an important parameter for tokamak design.Purpose: The purpose is to analyze radiation damage on the FWs and the out board blanket structure material on the equatorial plane through primary neutronic evaluation for CFETR to select a better armor material in two candidates-beryllium and tungsten.Methods: McCAD is used to convert the Computer Aided Design (CAD) model to Monte Carlo geometry model. And Monte Carlo particle transportation method is used to calculate the neutron radiation damage.Results:The results cover the neutron radiation damage distribution of first walls and the structure material of CFETR outboard blanket. Conclusion: Tungsten is better than beryllium to be the material of blanket first wall armor because has a better protection for blanket structure materials. The calculation results indicate that divertor and structure material of  CFETR blanket can satisfy the radiation damage standard in 8 a’s testing stage.%中国聚变工程实验堆(Chinese Fusion Engineering Testing Reactor, CFETR)的包层和偏滤器第一壁面向堆芯等离子体，第一壁辐照损伤分析对于托克马克安全运行至关重要。赤道面外包层较其它包层距离堆芯等离子体中心更近，其结构材料承受中子辐照大。因此，进行中子辐照损伤评估十分必要。基于此目的，采用计算机辅助设计(Computer Aided Design, CAD)模型和蒙特卡罗中子学建模转换接口McCAD完成中子学建模，并用蒙特卡罗方法的粒子输运程序计算第一壁和氦冷固态外包层结构材料辐照损伤。此外，对比了铍和钨作为面向等离子体材料两种情况下第一壁的受损情况。计算结果表明，氦冷固态包层模型下结构材料可以满足CFETR一期的运行要求。