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
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 46 条
  • [41] Tensile properties of the NLF reduced activation ferritic/martensitic steels after irradiation in a fast reactor spectrum to a maximum dose of 67 dpa
    Maloy, SA
    James, MR
    Romero, TJ
    Toloczko, MB
    Kurtz, RJ
    Kimura, A
    JOURNAL OF NUCLEAR MATERIALS, 2005, 341 (2-3) : 141 - 147
  • [42] Effects of helium on ductile-brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature
    Hasegawa, A.
    Ejiri, M.
    Nogami, S.
    Ishiga, M.
    Kasada, R.
    Kimura, A.
    Abe, K.
    Jitsukawa, S.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 241 - 244
  • [43] IMPACT PROPERTIES OF LOW ACTIVATION VANADIUM ALLOY AFTER LOW-TEMPERATURE NEUTRON IRRADIATION AT 450 °C AND BELOW
    Nagasaka, Takuya
    Muroga, Takeo
    Miyazawa, Takeshi
    Watanabe, Hideo
    Yamazaki, Masanori
    FUSION SCIENCE AND TECHNOLOGY, 2011, 60 (01) : 379 - 383
  • [44] MECHANICAL PROPERTIES OF TWO IMPROVED EUROFER ODS STEELS BEFORE AND AFTER LOW DOSE NEUTRON IRRADIATION AT 300 °C
    Lucon, Enrico
    FUSION SCIENCE AND TECHNOLOGY, 2009, 56 (01) : 289 - 294
  • [45] Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiation
    Dai, Y
    Maloy, SA
    Bauer, GS
    Sommer, WF
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) : 513 - 517
  • [46] Effect of helium on tensile properties and microstructure in 9%Cr-WVTa-steel after neutron irradiation up to 15 dpa between 250 and 450 °C
    Materna-Morris, E.
    Moeslang, A.
    Rolli, R.
    Schneider, H. -C.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 422 - 425