Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250-450°C

被引：33
作者：
Alamo, A [1 ]
Horsten, M
Averty, X
Materna-Morris, EI
Rieth, M
Brachet, JC
机构：
[1] CEA Saclay, SRMA, F-91191 Gif Sur Yvette, France
[2] NRG, NL-1755 ZG Petten, Netherlands
[3] CEA Saclay, DMT, SEMI, F-91191 Gif Sur Yvette, France
[4] Forschungszentrum Karlsruhe, Inst Mat Forsch, D-76021 Karlsruhe, Germany
来源：
JOURNAL OF NUCLEAR MATERIALS | 2000年 / 283卷 / PART I期
关键词：
D O I：
10.1016/S0022-3115(00)00076-3
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The objective of this work is to examine the susceptibility to hardening and embrittlement of Fe7.5/11CrWTaV reduced-activation (RA) and conventional 9/12Cr-Mo martensitic steels as a function of fluence up to 10 dpa and irradiation temperature in the range of 250-450 degreesC. For this purpose, materials were irradiated in the Osiris Reactor (Saclay) at 325 degreesC for Various doses ranging from 0.8 dpa to a maximum dose of 8-9 dpa. Available data concern the evolution of tensile properties for doses from 0.8 to 3.4 dpa. On the other hand, RA-steels were irradiated as Charpy V and tensile specimens in the high flux reactor (HFR) at Petten at temperatures ranging from 250 degreesC to 450 degreesC with a dose of about 2.4 dpa. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：353 / 357
页数：5
相关论文
共 11 条
[1]   OPTIMUM ALLOY COMPOSITIONS IN REDUCED-ACTIVATION MARTENSITIC 9CR STEELS FOR FUSION-REACTOR [J].
ABE, F ;
NODA, T ;
OKADA, M .
JOURNAL OF NUCLEAR MATERIALS, 1992, 195 (1-2) :51-67
[2]   Physical metallurgy and mechanical behaviour of FeCrWTaV low activation martensitic steels: Effects of chemical composition [J].
Alamo, A ;
Brachet, JC ;
Castaing, A ;
Lepoittevin, C ;
Barcelo, F .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1228-1235
[3]  
AVERTY X, 1998, P INT S FONT 4 CONTR, V1, pA74
[4]   Tensile and Charpy impact properties of irradiated reduced-activation ferritic steels [J].
Klueh, RL ;
Alexander, DJ .
EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 :911-930
[5]   The effect of tantalum on the mechanical properties of a 9Cr-2W-0.25V-0.07Ta-0.1C steel [J].
Klueh, RL ;
Alexander, DJ ;
Rieth, M .
JOURNAL OF NUCLEAR MATERIALS, 1999, 273 (02) :146-154
[6]  
KLUEH RL, 1994, P IEA WORK GROUP M F
[7]   Low-activation ferritic and martensitic steels for fusion application [J].
Kohyama, A ;
Hishinuma, A ;
Gelles, DS ;
Klueh, RL ;
Dietz, W ;
Ehrlich, K .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :138-147
[8]   Mechanical properties and microstructure of HFR-irradiated ferritic/martensitic low-activation alloys [J].
Materna-Morris, EI ;
Rieth, M ;
Ehrlich, K .
EFFECTS OF RADIATION ON MATERIALS: 19TH INTERNATIONAL SYMPOSIUM, 2000, 1366 :597-611
[9]   Embrittlement behaviour of different international low activation alloys after neutron irradiation [J].
Rieth, M ;
Dafferner, B ;
Rohrig, HD .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1147-1152
[10]   Fracture toughness and tensile behavior of ferritic-martensitic steels irradiated at low temperatures [J].
Rowcliffe, AF ;
Robertson, JP ;
Klueh, RL ;
Shiba, K ;
Alexander, DJ ;
Grossbeck, ML ;
Jitsukawa, S .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1275-1279
12