Generalized creep model of Zircaloy-4 cladding tubes

被引:18
|
作者
Kim, YS [1 ]
机构
[1] Korea Atom Energy Res Inst, Yusong Gu, Taejon 305600, South Korea
关键词
D O I
10.1016/S0022-3115(97)00261-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Zircaloy-4 cladding tubes with different area reductions at the final cold working were subjected to creep testing at temperatures of 350 to 500 degrees C. The creep testing was carried out mainly at the biaxial stress state. The creep rate and creep strain of the Zircaloy-4 cladding tube increased with increasing area reduction at the final cold working. The creep model was derived to cover the effect of area reduction and then verified by using supplementary creep data obtained at 350 degrees C and 138 MPa. Furthermore, this generalized creep model was verified to well describe the thermal creep of Duplex tubes and low Sn Zircaloy-3 tubes. The creep rate of Zircaloy-4 cladding tubes followed the exponential stress dependence, not the power law creep. The creep activation energy was determined to be 60 kcal/mol, leading to the conclusion that creep is controlled by dislocation creep. Thus, it is suggested that the increase of creep rates and creep strains with the increase in cold working is due to an enhanced climb rate arising from the increased concentration of vacancy. (C) 1997 Elsevier Science B.V.
引用
收藏
页码:164 / 170
页数:7
相关论文
共 50 条
  • [1] Impact of hydrogen on plasticity and creep of unirradiated zircaloy-4 cladding tubes
    Bouffioux, P
    Rupa, N
    ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 : 399 - 422
  • [2] CREEP COLLAPSE OF ZIRCALOY-4 CLADDING
    PAPAZOGLOU, TP
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 19 (OCT27): : 143 - 144
  • [3] Understanding the role of hydrogen on creep behaviour of Zircaloy-4 cladding tubes using nanoindentation
    Suman, Siddharth
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (09) : 2041 - 2046
  • [4] A creep collapse model for thin-walled Zircaloy-4 tubes
    Paun, VP
    REVUE ROUMAINE DE CHIMIE, 2003, 48 (11) : 903 - 906
  • [5] EX-REACTOR BIAXIAL CREEP OF ZIRCALOY-4 CLADDING
    CLEVINGER, GS
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 19 (OCT27): : 143 - 143
  • [6] The influence of a hydrided layer on the fracture of Zircaloy-4 cladding tubes
    Daum, RS
    Bates, DW
    Koss, DA
    Motta, AT
    HYDROGEN EFFECTS ON MATERIAL BEHAVIOR AND CORROSION DEFORMATION INTERACTIONS, 2003, : 249 - 258
  • [7] Fracture of Zircaloy-4 fuel cladding tubes with hydride blisters
    Macdonald, Vincent
    Le Boulch, David
    de Menibus, Arthur Hellouin
    Besson, Jacques
    Auzoux, Quentin
    Crepin, Jerome
    Le Jolu, Thomas
    20TH EUROPEAN CONFERENCE ON FRACTURE, 2014, 3 : 233 - 238
  • [8] Formation and characterization of hydride blisters in Zircaloy-4 cladding tubes
    de Menibus, Arthur Hellouin
    Auzoux, Quentin
    Dieye, Ousmane
    Berger, Pascal
    Bosonnet, Sophie
    Foy, Eddy
    Macdonald, Vincent
    Besson, Jacques
    Crepin, Jerome
    JOURNAL OF NUCLEAR MATERIALS, 2014, 449 (1-3) : 132 - 147
  • [9] Release of fission tritium through Zircaloy-4 fuel cladding tubes
    Andrieu, C
    Ravel, S
    Ducros, G
    Lemaignan, C
    JOURNAL OF NUCLEAR MATERIALS, 2005, 347 (1-2) : 12 - 19
  • [10] Research on nodular corrosion resistance performance of zircaloy-4 cladding tubes
    Lu, Hua-Quan
    Pang, Hua
    Zhao, Wen-Jin
    Ding, Zhi-Feng
    Zhang, Feng-Lin
    Tian, Sheng
    2003, Atomic Energy Publishing House (37):