Bi-directional hydrogen isotopes permeation through a reduced activation ferritic steel F82H

被引:13
作者
Xu, Yue [1 ]
Hirooka, Yoshi [1 ,2 ]
Nagasaka, Takuya [1 ,2 ]
机构
[1] Grad Univ Adv Studies, 322-6 Oroshi, Toki, Gifu 5095292, Japan
[2] Natl Inst Fus Sci, 322-6 Oroshi, Toki, Gifu 5095292, Japan
关键词
First wall; F82H; Gas- and plasma-driven permeation; Transport parameters; Isotopic effect; MARTENSITIC STEEL; DRIVEN PERMEATION; STAINLESS-STEELS; BLANKET DESIGNS; ALLOY F82H; 1ST WALL; DEUTERIUM; DIFFUSION; REACTOR; SOLUBILITY;
D O I
10.1016/j.fusengdes.2017.04.022
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
The first wall of a magnetic fusion reactor serves to separate the edge plasma from breeding blankets, which will be subjected to bi-directional hydrogen isotopes permeation: in one direction by plasma driven permeation, and in the other direction by gas-driven permeation. In this work, hydrogen isotopes transport through a reduced activation ferritic steel F82H has been investigated in the temperature range of 150-500 degrees C. The transport parameters including permeability, diffusivity, solubility and surface recombination coefficient have been measured and the isotopic mass effect has been discussed. Bi-directional hydrogen isotopes gas- and plasma-driven permeation has been demonstrated for the first time under controlled experimental conditions. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:343 / 348
页数:6
相关论文
共 29 条
[1]  
BIRNBAUM HK, 1972, BERICH BUNSEN GESELL, V76, P806
[3]   STEADY-STATE HYDROGEN TRANSPORT IN SOLIDS EXPOSED TO FUSION-REACTOR PLASMAS, .2. APPLICATIONS OF THEORY [J].
DOYLE, BL ;
BRICE, DK .
JOURNAL OF NUCLEAR MATERIALS, 1984, 123 (1-3) :1523-1530
[4]   The diffusivity and solubility of deuterium in a high chromium martensitic steel [J].
Forcey, KS ;
Iordanova, I ;
Yaneva, M .
JOURNAL OF NUCLEAR MATERIALS, 1997, 240 (02) :118-123
[5]   A new versatile facility: Vehicle-1 for innovative PFC concepts evaluation and its first experiments on hydrogen recycling from solid and liquid lithium [J].
Hirooka, Y ;
Ohgaki, H ;
Ohtsuka, Y ;
Nishikawa, M .
JOURNAL OF NUCLEAR MATERIALS, 2005, 337 (1-3) :585-589
[6]   LABORATORY EXPERIMENTS AND MODELING ON BI-DIRECTIONAL HYDROGEN ISOTOPES PERMEATION THROUGH THE FIRST WALL OF A MAGNETIC FUSION DEMO REACTOR [J].
Hirooka, Yoshi ;
Zhou, Haishan .
FUSION SCIENCE AND TECHNOLOGY, 2014, 66 (01) :63-69
[7]   PLASMA- AND GAS-DRIVEN HYDROGEN ISOTOPE PERMEATION THROUGH THE FIRST WALL OF A MAGNETIC FUSION POWER REACTOR [J].
Hirooka, Yoshi ;
Zhou, Haishan ;
Ashikawa, Naoko ;
Muroga, Takeo ;
Sagara, Akio .
FUSION SCIENCE AND TECHNOLOGY, 2013, 64 (02) :345-350
[8]   Review of blanket designs for advanced fusion reactors [J].
Ihli, T. ;
Basu, T. K. ;
Giancarli, L. M. ;
Konishi, S. ;
Malang, S. ;
Najmabadi, F. ;
Nishio, S. ;
Raffray, A. R. ;
Rao, C. V. S. ;
Sagara, A. ;
Wu, Y. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :912-919
[9]   Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests) [J].
Kulsartov, TV ;
Hayashi, K ;
Nakamichi, M ;
Afanasyev, SE ;
Shestakov, VP ;
Chikhray, YV ;
Kenzhin, EA ;
Kolbaenkov, AN .
FUSION ENGINEERING AND DESIGN, 2006, 81 (1-7) :701-705
[10]   Permeability, solubility and diffusivity of hydrogen isotopes in stainless steels at high gas pressures [J].
Marchi, C. San ;
Somerday, B. P. ;
Robinson, S. L. .
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2007, 32 (01) :100-116