STRUCTURAL MATERIAL REQUIREMENTS AND RELATED R-AND-D FOR ITER PLASMA-FACING COMPONENTS

被引:7
作者
BOUTARD, JL
机构
[1] The NET Team, Max-Planck-Institut für Plasmaphysik, D-8046 Garching bei München
关键词
D O I
10.1016/0022-3115(91)90317-Z
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Solution-annealed 316 type austenitic steels have been selected as structural material for the first wall and blanket of ITER, with cold-worked 316 and MnCr austenitic steels as candidate alloys. The effects of irradiation on their properties: tensile, fracture toughness, low cycle fatigue, creep and rupture, swelling, stress corrosion cracking and hydrogen embrittlement, are discussed in terms of the proposed ITER operating conditions. Arguments for the selection of oxide dispersion strengthened Cu alloy for divertor plates are presented. Finally, the investigations which are being undertaken within the ITER Technology Programme to provide additional data are reviewed.
引用
收藏
页码:1179 / 1184
页数:6
相关论文
共 36 条
[1]  
BERGENLID U, 1988, COMMUNICATION 0521
[2]   THE STRUCTURAL-MATERIALS FOR THE 1ST WALL AND PLASMA FACING COMPONENTS OF NET [J].
BOUTARD, JL .
JOURNAL OF NUCLEAR MATERIALS, 1990, 174 (2-3) :240-252
[3]  
BOUTARD JL, 1988, 15TH P S FUS TECHN U, P929
[4]   EFFECTS OF NEUTRON-IRRADIATION AT 450-DEGREES-C AND 16 DPA ON THE PROPERTIES OF VARIOUS COMMERCIAL COPPER-ALLOYS [J].
BRAGER, HR ;
HEINISCH, HL ;
GARNER, FA .
JOURNAL OF NUCLEAR MATERIALS, 1985, 133 (AUG) :676-679
[6]   TRITIUM-HELIUM EFFECTS IN METALS [J].
CASKEY, GR .
FUSION TECHNOLOGY, 1985, 8 (02) :2293-2298
[7]  
FRANCONI E, 1988, 15TH P S FUS TECHN U, P819
[8]  
Grossbeck M. L., 1991, J NUCL MATER, V179-181
[9]   AN ASSESSMENT OF TENSILE, IRRADIATION CREEP, CREEP-RUPTURE, AND FATIGUE BEHAVIOR IN AUSTENITIC STAINLESS-STEELS WITH EMPHASIS ON SPECTRAL EFFECTS [J].
GROSSBECK, ML ;
EHRLICH, K ;
WASSILEW, C .
JOURNAL OF NUCLEAR MATERIALS, 1990, 174 (2-3) :264-281
[10]   FATIGUE BEHAVIOR OF TYPE-316 STAINLESS-STEEL IRRADIATED IN A MIXED SPECTRUM FISSION REACTOR FORMING HELIUM [J].
GROSSBECK, ML ;
LIU, KC .
NUCLEAR TECHNOLOGY, 1982, 58 (03) :538-547