Present status of vanadium alloys for fusion applications

被引：170

作者：

Muroga, T. ^{[1
]}

Chen, J. M. ^{[2
]}

Chernov, V. M. ^{[3
]}

Kurtz, R. J. ^{[4
]}

Le Flem, M. ^{[5
]}

机构：

[1] Natl Inst Nat Sci, Natl Inst Fus Sci, Toki, Gifu 5095292, Japan

[2] Southwestern Inst Phys, Chengdu 610041, Peoples R China

[3] AA Bochvar High Technol Res Inst Inorgan Mat, Moscow 123060, Russia

[4] Pacific NW Natl Lab, Richland, WA 99354 USA

[5] CEA, DEN, DMN, F-91191 Gif Sur Yvette, France

来源：

JOURNAL OF NUCLEAR MATERIALS | 2014年 / 455卷 / 1-3期

关键词：

MECHANICAL-PROPERTIES; IMPACT PROPERTIES; V-4CR-4TI ALLOY; HYDROGEN; SOLUBILITY; MICROSTRUCTURE; 1ST-PRINCIPLES; MONOVACANCY; FABRICATION; DEUTERIUM;

D O I：

10.1016/j.jnucmat.2014.06.025

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Vanadium alloys are advanced options for low activation structural materials. After more than two decades of research, V-4Cr-4Ti has been emerged as the leading candidate, and technological progress has been made in reducing the number of critical issues for application of vanadium alloys to fusion reactors. Notable progress has been made in fabricating alloy products and weld joints without degradation of properties. Various efforts are also being made to improve high temperature strength and creep-rupture resistance, low temperature ductility after irradiation, and corrosion resistance in blanket conditions. Future research should focus on clarifying remaining uncertainty in the operating temperature window of V-4Cr-4Ti for application to near to middle term fusion blanket systems, and on further exploration of advanced materials for improved performance for longer-term fusion reactor systems. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：263 / 268

页数：6

共 53 条

[1] Hydrogen solubility in V-4Cr-4Ti alloy [J].

Buxbaum, RE ;

Smith, DL ;

Park, JH .

JOURNAL OF NUCLEAR MATERIALS, 2002, 307 :576-579

[2] An overview of the oxidation performance of suicide diffusion coatings for vanadium-based alloys for generation IV reactors [J].

Chaia, N. ;

Mathieu, S. ;

Cozzika, T. ;

Rouillard, F. ;

Desgranges, C. ;

Courouau, J. L. ;

Petitjean, C. ;

David, N. ;

Vilasi, M. .

CORROSION SCIENCE, 2013, 66 :285-291

[3] Overview of the vanadium alloy researches for fusion reactors [J].

Chen, J. M. ;

Chernov, V. M. ;

Kurtz, R. J. ;

Muroga, T. .

JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :289-294

[4]

Chernov V.M., INFNT 11

[5] CORROSION BEHAVIOR OF VANADIUM ALLOYS IN FLOWING LITHIUM [J].

CHOPRA, OK ;

SMITH, DL .

JOURNAL OF NUCLEAR MATERIALS, 1988, 155 :683-689

[6] French investigation of a new V-4Cr-4Ti grade: CEA-J57 - Fabrication and microstructure [J].

Duquesnes, Vincent ;

Guilbert, Thomas ;

Le Flem, Marion .

JOURNAL OF NUCLEAR MATERIALS, 2012, 426 (1-3) :96-101

[7] Fabrication using electron beam melting of a V-4Cr-4Ti alloy and its thermo-mechanical strengthening study [J].

Fu, H. Y. ;

Chen, J. M. ;

Zheng, P. F. ;

Nagasaka, T. ;

Muroga, T. ;

Li, Z. D. ;

Cui, S. ;

Xu, Z. Y. .

JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :S336-S340

[8] Effects of grain size on high temperature creep of fine grained, solution and dispersion hardened V-1.6Y-8W-0.8TiC [J].

Furuno, T. ;

Kurishita, H. ;

Nagasaka, T. ;

Nishimura, A. ;

Muroga, T. ;

Sakamoto, T. ;

Kobayashi, S. ;

Nakai, K. ;

Matsuo, S. ;

Arakawa, H. .

JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :299-302

[9] Development of techniques for welding V-Cr-Ti alloys [J].

Grossbeck, ML ;

King, JF ;

Alexander, DJ ;

Rice, PM ;

Goodwin, GM .

JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1369-1374

[10] First-principles investigation on vacancy trapping behaviors of hydrogen in vanadium [J].

Gui, Li-Jiang ;

Liu, Yue-Lin ;

Wang, Wei-Tian ;

Jin, Shuo ;

Zhang, Ying ;

Lu, Guang-Hong ;

Yao, Jun-En .

JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :S688-S693

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