Irradiation creep behavior of V-4Cr-4Ti alloys irradiated in a liquid sodium environment at the JOY fast reactor

被引:7
|
作者
Fukumoto, Ken-ichi [1 ]
Matsui, Hideki [2 ]
Narui, Minoru [3 ]
Yamazaki, Masanori [3 ]
机构
[1] Univ Fukui, Res Inst Nucl Engn, Fukui 9140055, Japan
[2] Kyoto Univ, Inst Adv Energy, Uji, Kyoto 6110011, Japan
[3] Tohoku Univ, Int Res Ctr Nucl Mat Sci, Oarai, Ibaraki 3111313, Japan
关键词
BIAXIAL THERMAL CREEP; VANADIUM-BASE ALLOYS; FUSION HEATS; STEELS; 800-DEGREES-C; 700-DEGREES-C; DEFORMATION; TEMPERATURE; 9CR-1MO; HELIUM;
D O I
10.1016/j.jnucmat.2013.02.012
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Irradiation experiments on V-4Cr-4Ti alloys with sodium-enclosed irradiation capsules in the JOYO fast reactor were conducted using pressurized creep tubes (PCTs). The irradiation creep strain was significantly larger than the thermal creep strain below 686 degrees C, but there was no swelling of the neutron-irradiated V-4Cr-4Ti alloys. At temperatures below 500 degrees C, the irradiation creep was found to be proportional to the square root of the neutron dose and linear with the stress level. Above 500 degrees C, it was expected to be proportional to the stress level to a power greater than unity, because the irradiation creep mechanism could change from the stress-induced preferred absorption mechanism (SIPA) to the preferred absorption glide mechanism (PGA). By comparing annealed PCT specimens with cold-worked specimens, the cold-worked V-4Cr-4Ti alloys exhibited a larger irradiation creep strain compared with the annealed alloys. The irradiation creep compliance of the V-4Cr-4Ti alloys were 10 x 10(-6) MPa-1 dpa(-1) below 500 degrees C and 50-200 x 10(-6) MPa-1 dpa(-1) above 500 degrees C, a value greater than that of commercial V-4Cr-4Ti alloys, austenitic steels and ferritic steels. 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:341 / 349
页数:9
相关论文
共 50 条
  • [41] Microstructure of creep-deformed V-4Cr-4Ti strengthened by precipitation and cold rolling
    Muroga, T.
    Nagasaka, T.
    Chen, J. M.
    Li, Y. F.
    Watanabe, H.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 606 - 609
  • [42] Characterization of interface irradiation damage in Ti-clad V-4Cr-4Ti composite material
    Li Ran-Ran
    Zhang Yi-Fan
    Geng Dian-Cheng
    Zhang Gao-Wei
    Watanabe, Hideo
    Han Wen-Tuo
    Wan Fa-Rong
    ACTA PHYSICA SINICA, 2019, 68 (21)
  • [43] Tritium diffusion in V-4Cr-4Ti alloy
    Hashizume, K.
    Masuda, J.
    Otsuka, K. T.
    Tanabe, T.
    Hatano, Y.
    Nakamura, Y.
    Nagasaka, T.
    Muroga, T.
    FUSION SCIENCE AND TECHNOLOGY, 2008, 54 (02) : 553 - 556
  • [44] Hydrogen solubility in V-4Cr-4Ti alloy
    Buxbaum, RE
    Smith, DL
    Park, JH
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 : 576 - 579
  • [45] Study of the micromechanical behaviour of irradiated V-4Cr-4Ti by in-situ microcolumn compression
    Jiang, Shaoning
    Zhang, Shoushuai
    Wang, Chaofeng
    Lin, Jianghai
    Guo, Liping
    Yin, Zepeng
    Zheng, Pengfei
    MATERIALS LETTERS, 2023, 348
  • [46] Deuterium Permeation Through Reduced Activation V-4Cr-4Ti Alloy and V-4Cr-4Ti Alloy with AlN/Al Coatings
    D. I. Cherkez
    A. V. Spitsyn
    A. V. Golubeva
    O. I. Obrezkov
    S. S. Ananyev
    N. P. Bobyr
    V. M. Chernov
    Physics of Atomic Nuclei, 2019, 82 : 1010 - 1024
  • [47] Manufacturing pressurized creep tubes from highly purified V-4Cr-4Ti alloys, NIFS-Heat2
    Fukumoto, K
    Matsui, H
    Narui, M
    Nagasaka, T
    Muroga, T
    JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (01) : 103 - 107
  • [48] Deuterium Permeation Through Reduced Activation V-4Cr-4Ti Alloy and V-4Cr-4Ti Alloy with AlN/Al Coatings
    Cherkez, D. I.
    Spitsyn, A. V.
    Golubeva, A. V.
    Obrezkov, O. I.
    Ananyev, S. S.
    Bobyr, N. P.
    Chernov, V. M.
    PHYSICS OF ATOMIC NUCLEI, 2019, 82 (07) : 1010 - 1024
  • [49] Effect of small additional elements on DBTT of V-4Cr-4Ti irradiated at low temperatures
    Shibayama, T
    Yamagata, I
    Kayano, H
    Namba, C
    JOURNAL OF NUCLEAR MATERIALS, 1998, 258 : 1361 - 1368
  • [50] Effect of oxygen on the crack growth behavior of V-4Cr-4Ti at 600°C
    Kurtz, RJ
    JOURNAL OF NUCLEAR MATERIALS, 2000, 283 : 822 - 826