Irradiation hardening of reduced activation martensitic steels

被引:39
作者
Kimura, A [1 ]
Morimura, T [1 ]
Narui, M [1 ]
Matsui, H [1 ]
机构
[1] TOHOKU UNIV, INST MAT RES, OARAI BRANCH, OARAI, IBARAKI 31113, JAPAN
关键词
D O I
10.1016/S0022-3115(96)00233-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Irradiation response on the tensile properties of 9Cr-2W steels has been investigated following FFTF/MOTA irradiations at temperatures between 646 and 873 K up to doses between 10 and 59 dpa, The largest irradiation hardening accompanied by the largest decrease in the elongation is observed for the specimens irradiated at 646 K at doses between 10 and 15 dpa. The irradiation hardening appears to saturate at a dose of around 10 dpa at the irradiation temperature. No hardening but softening was observed in the specimens irradiated at above 703 K to doses of 40 and 59 dpa. Microstructural observation by transmission electron microscope (TEM) revealed that the dislocation loops with the a[100] type Burgers vector and small precipitates which were identified to be M(6)C type carbides existed after the irradiation at below 703 K, As for the void formation, the average size of voids increased with increasing irradiation temperature from 646 to 703 K. No voids were observed above 703 K. Irradiation softening was attributed to the enhanced recovery of martensitic structure under the irradiation. Post-irradiation annealing resulted in hardening by the annealing at 673 K and softening by the annealing at 873 K.
引用
收藏
页码:319 / 325
页数:7
相关论文
共 19 条
[1]   ALLOY COMPOSITION SELECTION FOR IMPROVING STRENGTH AND TOUGHNESS OF REDUCED ACTIVATION 9CR-W STEELS [J].
ABE, F ;
NODA, T ;
ARAKI, H ;
NAKAZAWA, S .
JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :663-666
[2]   EFFECT OF CARBON ON IRRADIATION HARDENING OF REDUCED-ACTIVATION 10CR-30MN AUSTENITIC STEELS [J].
ABE, F ;
GARNER, FA ;
KAYANO, H .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 (pt A) :760-765
[3]   THE DEVELOPMENT OF FERRITIC-MARTENSITIC STEELS WITH REDUCED LONG-TERM ACTIVATION [J].
EHRLICH, K ;
KELZENBERG, S ;
ROHRIG, HD ;
SCHAFER, L ;
SCHIRRA, M .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :678-683
[4]  
GELLES DS, COMMUNICATION
[5]   IRRADIATION EMBRITTLEMENT OF NEUTRON-IRRADIATED LOW ACTIVATION FERRITIC STEELS [J].
KAYANO, H ;
KIMURA, A ;
NARUI, M ;
SASAKI, Y ;
SUZUKI, Y ;
OHTA, S .
JOURNAL OF NUCLEAR MATERIALS, 1988, 155 (pt B) :978-981
[6]   CHARPY IMPACT TESTING USING MINIATURE SPECIMENS AND ITS APPLICATION TO THE STUDY OF IRRADIATION BEHAVIOR OF LOW-ACTIVATION FERRITIC STEELS [J].
KAYANO, H ;
KURISHITA, H ;
KIMURA, A ;
NARUI, M ;
YAMAZAKI, M ;
SUZUKI, Y .
JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :425-428
[7]   EFFECTS OF SMALL CHANGES IN ALLOY COMPOSITION ON THE MECHANICAL-PROPERTIES OF LOW ACTIVATION 9-PERCENT CR-2-PERCENT W STEEL [J].
KAYANO, H ;
KIMURA, A ;
NARUI, M ;
KIKUCHI, T ;
OHTA, S .
JOURNAL OF NUCLEAR MATERIALS, 1991, 179 :671-674
[8]   DEPENDENCE OF GRAIN-BOUNDARY CHEMISTRY ON THE IRRADIATION DOSE IN LOW-ACTIVATION FERRITICS [J].
KIMURA, A ;
CHARLOT, LA ;
GELLES, DS ;
JONES, RH .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :725-729
[9]   DIMENSIONAL CHANGES AND MICROSTRUCTURE OF IN-PILE CREPT FERRITIC-MARTENSITIC STEEL [J].
KIMURA, A ;
GELLES, DS ;
KOHYAMA, A ;
PUIGH, RJ .
MATERIALS TRANSACTIONS JIM, 1993, 34 (11) :1069-1075
[10]   DESIGNATION OF ALLOY COMPOSITION OF REDUCED-ACTIVATION MARTENSITIC STEEL [J].
KIMURA, A ;
KAYANO, H ;
MISAWA, T ;
MATSUI, H .
JOURNAL OF NUCLEAR MATERIALS, 1994, 212 :690-694