Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench

被引:19
|
作者
Kim, JH [1 ]
Lee, MH [1 ]
Choi, BK [1 ]
Jeong, YH [1 ]
机构
[1] Korea Atom Energy Res Inst, Zirconium Fuel Cladding Team, Taejon 305600, South Korea
关键词
D O I
10.1016/j.nucengdes.2004.08.030
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
Simulated loss of coolant accident (LOCA) tests on Zircaloy-4 cladding were carried out to evaluate the thermal shock property during the injection of emergency core coolant. A Zircaloy-4 specimen was oxidized in a steam environment between 1000 and 1250 degreesC followed by a flooding of the cooling water. After the test, the ductility of the thermally embrittled specimen was measured by a ring-compression test and a microstructural analysis was carried out. The results showed that the threshold equivalent cladding reacted (ECR) value to cause a failure was higher than the conventional 17% criterion calculated by the Baker-Just equation. A residual metal thickness under 0.3 mm as well as a ring-compression ductility below 0.2 mm for a fracture is effective to assess the thermal shock embrittlement of Zircaloy-4 in an axially unrestrained, or even in a restrained condition. (C) 2004 Elsevier B.V. All rights reserved.
引用
收藏
页码:67 / 75
页数:9
相关论文
共 50 条
  • [41] Oxidation Behavior Characterization of Zircaloy-4 Cladding with Different Hydrogen Concentrations at 500-800 °C in an Ambient Atmosphere
    Yung, Tung-Yuan
    Lu, Wen-Fang
    Tsai, Kun-Chao
    Chuang, Cheng-Hao
    Chen, Po-Tuan
    MATERIALS, 2022, 15 (09)
  • [42] A comparative study of hydride-induced embrittlement of Zircaloy-4 fuel cladding tubes in the longitudinal and hoop directions
    Zhao, Zishou
    Kunii, Daichi
    Abe, Tomonori
    Yang, Huilong
    Shen, Jingjie
    Shinohara, Yasunari
    Kano, Sho
    Matsukawa, Yoshitaka
    Satoh, Yuhki
    Abe, Hiroaki
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, 54 (04) : 490 - 499
  • [43] Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing
    Yan, Yong
    Massey, Caleb P.
    Garrison, Ben E.
    Taller, Stephen A.
    Kang, Soyoung
    Nelson, Andrew T.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2024, 914
  • [44] An evaluation of hydrided Zircaloy-4 cladding fracture behavior by X-specimen test
    Hsu, Hsiao-Hung
    JOURNAL OF ALLOYS AND COMPOUNDS, 2006, 426 (1-2) : 256 - 262
  • [45] Behavior of pre-hydrided zircaloy-4 cladding under simulated LOCA conditions
    Nagase, F
    Fuketa, T
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2005, 42 (02) : 209 - 218
  • [46] Enhanced stress relaxation behavior via basal ( a ) dislocation activity in Zircaloy-4 cladding
    Nelson, Malachi
    Samuha, Shmuel
    Kombaiah, Boopathy
    Kamerman, David
    Hosemann, Peter
    JOURNAL OF NUCLEAR MATERIALS, 2024, 601
  • [47] Simulation of radioactivation and chlorination reaction behavior for Zircaloy-4 and Zirlo cladding hull wastes
    Jeon, Min Ku
    Park, Chang Je
    Lee, Chang Hwa
    Kang, Kweon Ho
    Park, Geun Il
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2012, 292 (03) : 1221 - 1228
  • [48] Determination of the initial oxidation behavior of Zircaloy-4 by in-situ TEM
    Harlow, Wayne
    Ghassemi, Hessam
    Taheri, Mitra L.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 474 : 126 - 133
  • [49] Simulation of radioactivation and chlorination reaction behavior for Zircaloy-4 and Zirlo cladding hull wastes
    Min Ku Jeon
    Chang Je Park
    Chang Hwa Lee
    Kweon Ho Kang
    Geun Il Park
    Journal of Radioanalytical and Nuclear Chemistry, 2012, 292 : 1221 - 1228
  • [50] Degradation of the mechanical properties of Zircaloy-4 due to hydrogen embrittlement
    Bertolino, G
    Meyer, G
    Ipiña, JP
    JOURNAL OF ALLOYS AND COMPOUNDS, 2002, 330 : 408 - 413