Surface condition effects on tritium permeation through the first wall of a water-cooled ceramic breeder blanket

被引:2
|
作者
Zhou, H. -S. [1 ]
Xu, Y. -P. [2 ]
Liu, H. -D. [2 ]
Liu, F. [1 ]
Li, X. -C. [1 ]
Zhao, M. -Z. [1 ]
Qi, Q. [1 ]
Ding, F. [1 ]
Luo, G. -N [1 ,2 ,3 ,4 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, POB 1126, Hefei, Peoples R China
[2] Univ Sci & Technol China, Grad Sch, Sci Isl Branch, POB 1126, Hefei, Peoples R China
[3] Hefei Ctr Phys Sci & Technol, POB 1126, Hefei, Peoples R China
[4] Chinese Acad Sci, Hefei Sci Ctr, POB 1126, Hefei, Peoples R China
基金
中国国家自然科学基金;
关键词
Tritium; First wall; Permeation; WCCB blanket; RAFMs; Tungsten; PLASMA-DRIVEN PERMEATION; STEEL ALLOY F82H; METAL INTERACTIONS; HYDROGEN; GAS; RECOMBINATION; INVENTORY; DESIGN; CFETR;
D O I
10.1016/j.fusengdes.2016.02.041
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Plasma-driven permeation of tritium (T) through the first wall of a water-cooled ceramic breeder (WCCB) blanket may raise safety and other issues. In the present work, surface effects on T transport through the first wall of a WCCB blanket have been investigated by theoretical calculation. Two types of wall structures, i.e., reduced activation ferritic/martensitic steels (RAFMs) walls with and without tungsten (W) armor, have been analyzed. Surface recombination is assumed to be the boundary condition for both the plasma-facing side and the coolant side. It has been found that surface conditions at both sides can affect T permeation flux and inventory. For the first wall using W as armor material, T permeation is not sensitive to the plasma-facing surface conditions. Contamination of the surfaces will lead to higher T inventory inside the first wall. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:586 / 589
页数:4
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