Deuterium transport in ITER-grade tungsten

被引:10
作者
Byeon, W. J. [1 ]
Noh, S. J. [2 ]
机构
[1] Korea Basic Sci Inst, Ctr Sci Instrumentat, Div Sci Instrumentat & Management, Chungbuk 28119, South Korea
[2] Dankook Univ, Dept Phys, Cheonan Si 31116, Chungnam, South Korea
基金
新加坡国家研究基金会;
关键词
ITER-grade tungsten; Commercial polycrystalline tungsten; Transport; Deuterium; Hydrogen isotopes; GAS-DRIVEN PERMEATION; HELIUM IRRADIATION; HYDROGEN; RETENTION; BEHAVIOR; PARAMETERS; DIFFUSION; PERMEABILITY; SURFACE; ALLOYS;
D O I
10.1016/j.jnucmat.2020.152675
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The transport behavior of hydrogen isotopes in ITER grade tungsten (IG-W) and commercial rolled polycrystalline tungsten (CR-W) was investigated using deuterium gas. Analyses using field-emission scanning electron microscopy revealed that both IG-W and CR-W had a polycrystalline structure, but their surface grain structures were apparently different. The permeability and diffusivity of deuterium in IG-W and CR-W were obtained using a time-dependent gas-phase technique in the temperature range of 650-850 degrees C, being observed to be affected by surface morphology and grain boundaries. Our results in this study were also compared with previous results for polycrystalline W reported by other authors. (C) 2020 Elsevier B.V. All rights reserved.
引用
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页数:6
相关论文
共 38 条
[1]   Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma [J].
Alimov, V. Kh. ;
Tyburska-Pueschel, B. ;
Lindig, S. ;
Hatano, Y. ;
Balden, M. ;
Roth, J. ;
Isobe, K. ;
Matsuyama, M. ;
Yamanishi, T. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 420 (1-3) :519-524
[2]  
[Anonymous], 2004, G74MA10010711W02 ITE
[3]   Deuterium retention and morphological modifications of the surface in five grades of tungsten after deuterium plasma exposure [J].
Balden, M. ;
Manhard, A. ;
Elgeti, S. .
JOURNAL OF NUCLEAR MATERIALS, 2014, 452 (1-3) :248-256
[4]   Hydrogen and deuterium transport and inventory parameters through W and W-alloys for fusion reactor applications [J].
Benamati, G ;
Serra, E ;
Wu, CH .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 :1033-1037
[5]   Gas-driven permeation of deuterium through tungsten and tungsten alloys [J].
Buchenauer, Dean A. ;
Karnesky, Richard A. ;
Fang, Zhigang Zak ;
Ren, Chai ;
Oya, Yasuhisa ;
Otsuka, Teppei ;
Yamauchi, Yuji ;
Whaley, Josh A. .
FUSION ENGINEERING AND DESIGN, 2016, 109 :104-108
[6]   Transport of hydrogen and deuterium in 316LN stainless steel over a wide temperature range for nuclear hydrogen and nuclear fusion applications [J].
Byeon, W. J. ;
Lee, S. K. ;
Noh, S. J. .
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2020, 45 (15) :8827-8832
[7]   Manufacturing influences on microstructure and fracture mechanical properties of polycrystalline tungsten [J].
Conte, M. ;
Aktaa, J. .
NUCLEAR MATERIALS AND ENERGY, 2019, 21
[8]  
Crank J., 1979, The Mathematics of Diffusion
[10]   Hydrogen isotope diffusive transport parameters in pure polycrystalline tungsten [J].
Esteban, GA ;
Perujo, A ;
Sedano, LA ;
Douglas, K .
JOURNAL OF NUCLEAR MATERIALS, 2001, 295 (01) :49-56