Tensile properties of ferritic/martensitic steels irradiated in STIP-I

被引:38
作者
Dai, Y. [1 ]
Long, B. [1 ]
Tong, Z. F. [1 ]
机构
[1] Paul Scherrer Inst, Spallat Neutron Source Div, CH-5232 Villigen, Switzerland
关键词
D O I
10.1016/j.jnucmat.2008.02.036
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Specimens of ferritic/martensitic (FM) steels T91, F82H, Optimax-A and the electron beam weld (EBW) of F82H were irradiated in the Swiss spallation neutron source (SINQ) Target-3 in a temperature range of 90-370 degrees C to displacement doses between 3 and 12 dpa. Tensile tests were performed at room temperature and the irradiation temperatures. The tensile test results demonstrated that the irradiation hardening increased with dose up to about 10 dpa. Meanwhile, the uniform elongation decreased to less than 1%, while the total elongation remained greater than 5%, except for an F82H specimen of 9.8 dpa tested at room temperature, which failed in elastic deformation regime. At higher doses of 11-12 dpa, the ductility of some specimens recovered, which could be due to the annealing effect of a short period of high temperature excursion. The results do not show significant differences in tensile properties for the different FM steels in the present irradiation conditions. (c) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:115 / 121
页数:7
相关论文
共 14 条
  • [1] The tensile properties of AISI 316L and OPTIFER in various conditions irradiated in a spallation environment
    Chen, J
    Rödig, M
    Carsughi, F
    Dai, Y
    Bauer, GS
    Ullmaier, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2005, 343 (1-3) : 236 - 240
  • [2] Mechanical properties of modified 9Cr-1Mo (T91) irradiated at ≤ 300 °C in SINQ Target-3
    Dai, Y
    Jia, XJ
    Farrell, K
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2003, 318 : 192 - 199
  • [3] Neutronics calculation, dosimetry analysis and gas measurements of the first SINQ target irradiation experiment, STIP-I
    Dai, Y
    Foucher, Y
    James, MR
    Oliver, BM
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2003, 318 : 167 - 175
  • [4] Status of the first SINQ irradiation experiment, STIP-I
    Dai, Y
    Bauer, GS
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2001, 296 : 43 - 53
  • [5] DAI Y, 1995, P ICANS 13 ESS PM4 1, P604
  • [6] Tensile properties of 9Cr-1Mo martensitic steel irradiated with high energy protons and neutrons
    Henry, J
    Averty, X
    Dai, Y
    Lamagnère, P
    Pizzanelli, JP
    Espinas, JJ
    Wident, P
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2003, 318 : 215 - 227
  • [7] Recommendation of miniaturized techniques for mechanical testing of fusion materials in an intense neutron source
    Jung, P
    Hishinuma, A
    Lucas, GE
    Ullmaier, H
    [J]. JOURNAL OF NUCLEAR MATERIALS, 1996, 232 (2-3) : 186 - 205
  • [8] KLUEH RL, 1992, AM SOC TEST MATER, V1125, P1256, DOI 10.1520/STP17944S
  • [9] IMPACT BEHAVIOR OF CR-W STEELS
    KLUEH, RL
    CORWIN, WR
    [J]. JOURNAL OF MATERIALS ENGINEERING, 1989, 11 (02) : 169 - 175
  • [10] KLUEH RL, 1996, P 1 INT WORKSH SPALL