Long-term properties of reduced activation ferritic/martensitic steels for fusion reactor blanket system

被引:46
|
作者
Shiba, Kiyoyuki [1 ]
Tanigawa, Hiroyasu [1 ]
Hirose, Takanori [1 ]
Sakasegawa, Hideo [1 ]
Jitsukawa, Shiro [1 ]
机构
[1] Japan Atom Energy Agcy, Tokai, Ibaraki 3191195, Japan
关键词
Reduced activation ferritic/martensitic steels; Thermal aging; TTP diagram; Tensile properties; Charpy impact properties;
D O I
10.1016/j.fusengdes.2011.06.005
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Thermal aging properties of reduced activation ferritic/martensitic steel F82H was researched. The aging was performed at temperature ranging from 400 degrees C to 650 degrees C up to 100,000 h. Microstructure, precipitates, tensile properties, and Charpy impact properties were carried out on aged materials. Laves phase was found at temperatures between 550 and 650 degrees C and M(6)C type carbides were found at the temperatures between 500 and 600 degrees C over 10,000 h. These precipitates caused degradation in toughness, especially at temperatures ranging from 550 degrees C to 650 degrees C. Tensile properties do not have serious aging effect, except for 650 degrees C, which caused large softening even after 10,000h. Increase of precipitates also causes some degradation in ductility, but it is not critical. Large increase in ductile-to-brittle transition temperature was observed in the 650 degrees C aging. It was caused by the large Laves phase precipitation at grain boundary. Lives precipitates at grain boundary also degrades the upper-shelf energy of the aged materials. These aging test results indicate F82H can be used up to 30,000 h at 550 degrees C. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:2895 / 2899
页数:5
相关论文
共 50 条
  • [21] Strengthening mechanisms of reduced activation ferritic/martensitic steels:A review
    Jin-hua Zhou
    Yong-feng Shen
    Nan Jia
    InternationalJournalofMineralsMetallurgyandMaterials, 2021, 28 (03) : 335 - 348
  • [22] Strengthening mechanisms of reduced activation ferritic/martensitic steels: A review
    Jin-hua Zhou
    Yong-feng Shen
    Nan Jia
    International Journal of Minerals, Metallurgy and Materials, 2021, 28 : 335 - 348
  • [23] Low-activation ferritic and martensitic steels for fusion application
    Kyoto Univ, Kyoto, Japan
    J Nucl Mater, Pt A (138-147):
  • [24] Low-activation ferritic and martensitic steels for fusion application
    Kohyama, A
    Hishinuma, A
    Gelles, DS
    Klueh, RL
    Dietz, W
    Ehrlich, K
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 138 - 147
  • [25] Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors
    Tan, L.
    Snead, L. L.
    Katoh, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 478 : 42 - 49
  • [26] Development of low activation ferritic and martensitic steels for fusion reactors
    Kohyama, A
    Hishinuma, A
    Gelles, DS
    Klueh, RL
    Dietz, W
    Ehrlich, K
    FUSION ENERGY 1996, VOL 3, 1997, : 499 - 506
  • [27] Radiation effects on low cycle fatigue properties of reduced activation ferritic/martensitic steels
    Hirose, T
    Tarilgawa, H
    Ando, M
    Kohyama, A
    Katoh, Y
    Narui, M
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 304 - 307
  • [28] OXIDATION OF PEARLITIC AND FERRITIC-MARTENSITIC STEELS DURING LONG-TERM CREEP
    ZUSMAN, VM
    ANTIKAYN, PA
    BANNYKH, OA
    VOLKOVA, RM
    RUSSIAN METALLURGY, 1973, (04): : 110 - 113
  • [29] Reduced activation martensitic steels as a structural material for ITER test blanket
    Shiba, K
    Enoeda, M
    Jitsukawa, S
    JOURNAL OF NUCLEAR MATERIALS, 2004, 329 : 243 - 247
  • [30] Current status of reduced-activation ferritic/martensitic steels R&D for fusion energy
    Kimura, Akihiko
    Mater. Trans., 3 (394-404):