ITER氦冷固态实验包层模块第一壁氢同位素双向输运数值分析  

Numerical Analysis of Bi-Directional Hydrogen Isotopes Transport in First Wall of ITER Helium Coolant Ceramic Breeding Testing Blanket Module

作　　者：王俊[1] 张龙[1] 王晓宇[1] 武兴华[1] 李茹烟 WANG Jun;ZHANG Long;WANG Xiao-yu;WU Xing-hua;LI Ru-yan(Southwestern Institute of Physics,Chengdu 610225,China)

机构地区：[1]核工业西南物理研究院,四川成都610225

出　　处：《核化学与放射化学》2024年第2期125-130,I0004,共7页Journal of Nuclear and Radiochemistry

基　　金：四川省自然科学基金项目(NSFSC1234);中国氦冷固态实验包层资助项目;国家重点研发计划项目(2017YFE0300601)。

摘　　要：氦冷固态实验包层模块(HCCB-TBM)安装于国际热核聚变实验堆(ITER)中,用以验证HCCB包层概念的氚增殖能力与热移出能力。HCCB-TBM第一壁用于承受堆芯等离子体粒子轰击和包容内部功能材料。外侧等离子体驱动氘、氚粒子渗透与内侧氢分压驱动渗透的同时存在,形成了第一壁的双向氢同位素输运。此双向输运可能对第一壁外表面再循环系数、包层增殖氚的纯化产生重要影响。基于商业软件COMSOL建立第一壁双向氢同位素输运模型,研究第一壁的氢同位素的输运特征。仿真结果表明:第一壁中的冷却剂流道具有强的氢同位素移出能力,使得双向输运解耦合;在ITER等离子体脉冲周期中,放电过程中已扩散到材料内部的氚在等离子体关停时扩散回流到真空室侧,关停时的回流将降低向冷却剂流道的氚渗透损失。Helium-Cooled Ceramic Breeding Blanket Module(HCCB-TBM)will be installed on ITER machine to test its tritium breeding performance and thermal removal ability.The first wall of HCCB TBM is to handle the bombardment of plasma particles and confine the internal functional materials.The co-exist of plasma driven deuterium/tritium particle permeation from vacuum outside surface and hydrogen partial pressure driven permeation from inside surface forms the bi-directional transport of hydrogen isotopes of the first wall.This bi-directional transport would make the surface recycling parameter of outside surface and the purification of tritium from blanket bred zone much difference.A bi-directional hydrogen isotopes transport model is built to investigate the hydrogen transport performances of the first wall in the commercial software COMSOL.The simulation results show that the coolant channels in the first wall act as such an effective hydrogen isotopes removing dwell that the bi-directional transport is decoupled.During each ITER plasma pulse,part of the tritium deeply permeated into the first wall during discharge period will permeate backward to the vacuum side.As a result,the backward permeation during plasma dwell time would make a reduction to the tritium permeation loss to coolant channels.

关 键 词：HCCB-TBM 第一壁 氢同位素 双向输运 

分 类 号：TL62[核科学技术—核技术及应用]