Recent progress on development of vanadium alloys for fusion

被引:142
作者
Kurtz, RJ
Abe, K
Chernov, VM
Hoelzer, DT
Matsui, H
Muroga, T
Odette, GR
机构
[1] Pacific NW Natl Lab, Richland, WA 99352 USA
[2] Tohoku Univ, Dept Quantum Sci & Energy Engn, Sendai, Miyagi 9808579, Japan
[3] AA Bochvar Inorgan Mat Res Inst, Moscow, Russia
[4] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[5] Tohoku Univ, Inst Mat Res, Sendai, Miyagi 9808577, Japan
[6] Natl Inst Fus Sci, Gifu 5095292, Japan
[7] Univ Calif Santa Barbara, Dept Mech & Environm Engn, Santa Barbara, CA 93106 USA
关键词
D O I
10.1016/j.jnucmat.2004.04.299
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Considerable progress has been made toward development of vanadium alloys for fusion. Much of the recent research has focused on vanadium alloys containing 4-5% Cr and 4-5% Ti, but a number of alternative compositions and processing routes have been explored in an effort to achieve improved performance. The goal of this paper is to review significant new results and to highlight critical issues that remain for future research. Progress in understanding the influence of interstitial impurities on microstructural evolution in both thermal and radiation environments are covered. The current state of knowledge of hardening and embrittlement of vanadium alloys in response to neutron irradiation is reviewed. Atomic-scale computer simulations to elucidate fundamental irradiation damage mechanisms are presented. The thermal and irradiation creep behavior of V-4Cr-4Ti is summarized along with an overview of the effects of He on tensile properties. (C) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:47 / 55
页数:9
相关论文
共 56 条
[1]   Neutron irradiation experiments for fusion reactor materials through JUPITER program [J].
Abe, K ;
Kohyama, A ;
Namba, C ;
Wiffen, FW ;
Jones, RH .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :2075-2078
[2]   MODIFIED EMBEDDED-ATOM POTENTIALS FOR CUBIC MATERIALS AND IMPURITIES [J].
BASKES, MI .
PHYSICAL REVIEW B, 1992, 46 (05) :2727-2742
[3]  
BILLONE MC, 1997, DOEER031323, P3
[4]  
Braski D. N., 1987, ASTM STP, V956, P271
[5]  
BRASKI DN, 1990, AM SOC TEST MATER, V1047, P161, DOI 10.1520/STP24956S
[6]  
CHUNG HM, 1995, US CONTRIBUTION 1994, P87
[7]  
EHRLICH K, 1969, P IAEA C RAD DAMAGE, V2, P349
[8]   High temperature performance of highly purified V-4Cr-4Ti alloy, NIFS-Heat1 [J].
Fukumoto, K ;
Yamamoto, T ;
Nakao, N ;
Takahashi, S ;
Matsui, H .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) :610-614
[9]  
GELLES DS, 2001, DOEER031331, P17
[10]  
Grossbeck M. L., 1987, ASTM STP, V956, P291