Enhancement of irradiation hardening by nickel addition in the reduced-activation 9Cr-2W martensitic steel

被引:31
|
作者
Kasada, R [1 ]
Kimura, A
Matsui, H
Narui, M
机构
[1] Kyoto Univ, Inst Adv Energy, Dept Engn Sci, Kyoto 6110011, Japan
[2] Tohoku Univ, IMR, Aoba Ku, Sendai, Miyagi 98077, Japan
[3] Tohoku Univ, Inst Mat Res, Oarai Branch, Oarai, Ibaraki 31113, Japan
关键词
D O I
10.1016/S0022-3115(98)00186-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Reduced-activation martensitic (RAM) steels with and without an addition of 1% Ni were irradiated in a so called multisection-multidivision controlled irradiation capsule in the JMTR at 220 degrees C up to 0.15 dpa. The 1/4 power dependence of the irradiation hardening on neutron dose was observed for the specimens irradiated in the controlled capsule. A part of the specimens were simultaneously irradiated in the capsule out of the reactor core where the irradiation temperature was considered to be lower than 170 degrees C. The out of-reactor core irradiation induced a tremendous irradiation hardening as much as 350 MPa in the Ni added RAM steel but only 120 MPa of the hardening in the unadded RAM steel. The tremendous irradiation hardening was never observed following the irradiation at 220 degrees C. As for the results of positron annihilation measurements, no significant effect of the Ni addition was observed in the life time spectrum. Post-irradiation annealing studies indicate that the irradiation hardening observed in the Ni added RAM steel begins to recover at 190 degrees C and diminishes after the annealing at 250 degrees C. (C) 1998 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:1199 / 1203
页数:5
相关论文
共 50 条
  • [1] Enhancement of irradiation hardening by nickel addition in the reduced-activation 9Cr-2W martensitic steel
    Tohoku Univ, Sendai, Japan
    J Nucl Mater, pt B (1199-1203):
  • [2] Effects of varying temperature irradiation on the neutron irradiation hardening of reduced-activation 9Cr-2W martensitic steels
    Kasada, R.
    Kimura, A.
    Matsui, H.
    Hasegawa, M.
    Narui, M.
    Journal of Nuclear Materials, 1999, 271-272 : 360 - 364
  • [3] Effects of varying temperature irradiation on the neutron irradiation hardening of reduced-activation 9Cr-2W martensitic steels
    Kasada, R
    Kimura, A
    Matsui, H
    Hasegawa, M
    Narui, M
    JOURNAL OF NUCLEAR MATERIALS, 1999, 271 : 360 - 364
  • [4] Effect of helium implantation on mechanical properties and microstructure evolution of reduced-activation 9Cr-2W martensitic steel
    Kasada, R
    Morimura, T
    Hasegawa, A
    Kimura, A
    JOURNAL OF NUCLEAR MATERIALS, 2001, 299 (01) : 83 - 89
  • [5] Effect of Microstructures and Tempering Heat Treatment on the Mechanical Properties of 9Cr-2W Reduced-Activation Ferritic-Martensitic Steel
    Park, Min-Gu
    Moon, Joonoh
    Lee, Tae-Ho
    Kang, Nam Hyun
    Kim, Hyoung Chan
    Lee, Chang-Hoon
    KOREAN JOURNAL OF METALS AND MATERIALS, 2015, 53 (05): : 312 - 319
  • [6] Tensile Flow Behavior of 9Cr-2WVTa Reduced-Activation Ferritic/Martensitic Steel
    Najafi, Hamidreza
    JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 2016, 138 (03):
  • [7] The Irradiation Performance and Microstructural Evolution in 9Cr-2W Steel Under Ion Irradiation
    Sultan Alsagabi
    Indrajit Charit
    Somayeh Pasebani
    Journal of Materials Engineering and Performance, 2016, 25 : 401 - 408
  • [8] The Irradiation Performance and Microstructural Evolution in 9Cr-2W Steel Under Ion Irradiation
    Alsagabi, Sultan
    Charit, Indrajit
    Pasebani, Somayeh
    JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE, 2016, 25 (02) : 401 - 408
  • [9] THE ROLE OF MICROSTRUCTURAL INSTABILITY ON CREEP-BEHAVIOR OF A MARTENSITIC 9CR-2W STEEL
    ABE, F
    NAKAZAWA, S
    ARAKI, H
    NODA, T
    METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1992, 23 (02): : 469 - 477
  • [10] TENSILE PROPERTIES OF REDUCED-ACTIVATION FE-9CR-2W STEELS AFTER FFTF IRRADIATION
    KURISHITA, H
    KAYANO, H
    NARUI, M
    KIMURA, A
    HAMILTON, ML
    GELLES, DS
    JOURNAL OF NUCLEAR MATERIALS, 1994, 212 : 730 - 735