Status of vanadium alloys for fusion reactors

被引:142
作者
Matsui, H
Fukumoto, K
Smith, DL
Chung, HM
vanWitzenburg, W
Votinov, SN
机构
[1] ARGONNE NATL LAB, ARGONNE, IL 60439 USA
[2] ECN PETTEN, PETTEN, NETHERLANDS
[3] AA BOCHVAR INORGAN MAT RES INST, MOSCOW, RUSSIA
关键词
D O I
10.1016/S0022-3115(96)00331-5
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Advantages of vanadium alloys for fusion reactor structural applications are: low induced activation, excellent thermal stress factor, high strength at elevated temperatures, and superior ductility at low temperatures. Resistance to irradiation damage is also very impressive, i.e. very small DBTT shift by irradiation and low swelling, Research and development of vanadium alloys have made a remarkable progress in recent years partly supported by ITER-related activities, Composition range centered about V-4Cr-4Ti is the target of many of the studies conducted in the US, Japan and RF, Most of the studies have demonstrated the superior performance of this alloy family, while some alloys containing large amount of impurities have shown relatively poor properties. In addition to the baseline mechanical properties, neutron irradiation effects, e.g., swelling and radiation embrittlement are covered in this paper, Of particular importance is the study on the effects of dynamically-charged helium on mechanical properties and swelling. Recent developments of insulator coatings and welding are also covered. The importance of mechanistic studies of the damage behavior is emphasized for efficient alloy development and prediction of materials life in service.
引用
收藏
页码:92 / 99
页数:8
相关论文
共 27 条
[1]   THE EFFECT OF DIFFUSION ANISOTROPY ON DISLOCATION BIAS AND IRRADIATION CREEP IN CUBIC LATTICE MATERIALS [J].
BORODIN, VA ;
RYAZANOV, AI .
JOURNAL OF NUCLEAR MATERIALS, 1994, 210 (03) :258-267
[2]   EFFECT OF IRRADIATION DAMAGE AND HELIUM ON SWELLING AND STRUCTURE OF VANADIUM-BASE ALLOYS [J].
CHUNG, HM ;
LOOMIS, BA ;
SMITH, DL .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :804-812
[3]  
CHUNG HM, 1995, ANLFPPTM287, P61
[4]  
CHUNG HM, 1995, ANLFPPTM287, P11
[5]  
CHUNG HM, 1995, ANLFPPTM287, P53
[6]  
CHUNG HM, 1995, ANLFPPTM287, P147
[7]  
CHUNG HM, 1995, ANLFPPTM287, P175
[8]  
DELENE JG, 1991, FUSION TECHNOL, V19, P807
[9]  
FUKUMOTO K, UNPUB
[10]   AN MD SIMULATION OF INTERACTIONS BETWEEN SELF-INTERSTITIAL ATOMS AND EDGE DISLOCATION IN BCC TRANSITION-METALS [J].
KAMIYAMA, H ;
RAFIITABAR, H ;
KAWAZOE, Y ;
MATSUI, H .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :231-235