A normalization method for relationship between yield stress and delayed hydride cracking velocity in Zr-2.5Nb alloys

被引:0
|
作者
Oh, JK
Kim, IS
Kim, YS
机构
[1] Korea Adv Inst Sci & Technol, Taejon 305701, South Korea
[2] Korea Atom Energy Res Inst, Taejon 305353, South Korea
关键词
zirconium alloy; delayed hydride cracking; crack propagation; pressure tube; mechanical property; hydrogen embrittlement; yield strength; temperature dependence; stresses; activation energy;
D O I
10.1080/18811248.2000.9714935
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
The delayed hydride cracking (DHC) in pressure tube of CANDU reactors was measured on specimens which had different yield stresses. It is difficult to compare DHC velocities at different temperatures among materials with different yield stresses after heat-treatment or irradiation. To evaluate the effect of the yield stress on DHC velocity, a normalization method, based on Puls' DHC model, was proposed. When DHC velocity was normalized by dividing with the terminal solid solubility and the diffusion coefficient of hydrogen, the relationship between yield stress and DHC velocity was representable on one master curve. The equation from the master curve could explain the difference between theoretical activation energy and experimental activation energy in DHC. The difference was found to be ascribed to the decrease of yield stress with increasing temperature.
引用
收藏
页码:595 / 600
页数:6
相关论文
共 50 条
  • [31] Effect of Hydrogen Isotopes on Delayed Hydride Cracking Behavior of Zr-2.5Nb Pressure Tube Material
    A. K. Bind
    Saurav Sunil
    R. N. Singh
    Transactions of the Indian Institute of Metals, 2022, 75 : 2767 - 2775
  • [32] A microstructure-based modeling of delayed hydride cracking in Zr-2.5Nb pressure tube material
    Jha, Anjali
    Sarkar, Subrato
    Singh, I. V.
    Mishra, B. K.
    Singh, Ritu
    ENGINEERING FRACTURE MECHANICS, 2024, 295
  • [33] Delayed hydride cracking velocity of irradiated Zr-2.5Nb tubes after a 30-year operation in the Wolsong Unit 1
    Kim, YS
    Ahn, SB
    Im, KS
    Oh, WH
    PRICM 5: THE FIFTH PACIFIC RIM INTERNATIONAL CONFERENCE ON ADVANCED MATERIALS AND PROCESSING, PTS 1-5, 2005, 475-479 : 1409 - 1414
  • [34] Evaluation of variables affecting crack propagation by Delayed Hydride Cracking in Zr-2.5Nb with different heat treatments
    Mieza, J. I.
    Vigna, G. L.
    Domizzi, G.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 411 (1-3) : 150 - 159
  • [35] Crack initiation by delayed hydride cracking at sharp notches in Zr-2.5 NB alloys
    Sagat, S
    Newman, GW
    Scarth, DA
    HYDROGEN EFFECTS ON MATERIAL BEHAVIOR AND CORROSION DEFORMATION INTERACTIONS, 2003, : 289 - 299
  • [36] DEUTERIUM DISTRIBUTIONS ON DELAYED HYDRIDE CRACK FRACTURE SURFACES OF ZR-2.5NB
    LAURSEN, T
    PALMER, GR
    SHEK, GK
    JOURNAL OF NUCLEAR MATERIALS, 1995, 218 (02) : 210 - 216
  • [37] Anisotropic threshold stress intensity factor, KIH and crack growth rate in delayed hydride cracking of Zr-2.5Nb pressure tubes
    Young Suk Kim
    Sung Soo Kim
    Sang Chul Kwon
    Yong Moo Cheong
    Kyung Soo Im
    Metallurgical and Materials Transactions A, 2002, 33 : 919 - 925
  • [38] Anisotropic threshold stress intensity factor, KIH and crack growth rate in delayed hydride cracking of Zr-2.5Nb pressure tubes
    Kim, YS
    Kim, SS
    Kwon, SC
    Im, KS
    Cheong, YM
    METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2002, 33 (03): : 919 - 925
  • [39] Temperature dependence of threshold stress intensity factor, KIH in Zr-2.5Nb alloy and its effect on temperature limit for delayed hydride cracking
    Kim, Young Suk
    Ahn, Sang Bok
    Kim, Kang Soo
    Cheong, Yong Moo
    Experimental Mechanics in Nano and Biotechnology, Pts 1 and 2, 2006, 326-328 : 919 - 922
  • [40] Delayed hydride crack growth study on irradiated Zr-2.5Nb pressure tube
    Shah, Priti Kotak
    Dubey, J. S.
    Kumar, Ashwini
    Shriwastaw, R. S.
    Rath, B. N.
    Pandit, K. M.
    Dhotre, M. P.
    Mishra, P.
    Alur, V. D.
    Anantharaman, S.
    JOURNAL OF NUCLEAR MATERIALS, 2015, 460 : 1 - 4