Experimental Study of Cr-coated Zirconium Alloy Cladding under Simulated LOCA Conditions

被引：0
|
作者：
Wang, Zhanwei [1 ]
Yan, Jun [1 ]
Peng, Zhenxun [1 ]
Ren, Qisen [1 ]
Liao, Yehong [1 ]
Li, Sigong [1 ]
Zhao, Yahuan [1 ]
机构：
[1] Department of Nuclear Fuel & Material, China Nuclear Power Technology Research Institute Co., Ltd., Guangdong, Shenzhen,518026, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 02期
关键词：
Engineering Village;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Cr-coated zirconium alloy cladding - Ductile to brittle transitions - Fukushima nuclear accidents - High temperature steam oxidation - Highest temperature - Loss of coolant accident - Loss of coolant accident conditions - Loss-of-coolant-accident - Quenching - Steam oxidation
引用
收藏
页码：122 / 128
相关论文
共 50 条
  • [1] Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/ LOCA conditions
    Aragon, Pau
    Feria, Francisco
    Herranz, Luis E.
    Schubert, Arndt
    Van Uffelen, Paul
    ANNALS OF NUCLEAR ENERGY, 2025, 211
  • [2] Investigation on Corrosion Model of Cr-coated Zirconium Alloy Cladding
    Shen, Yong
    Zeng, Xiehu
    Duan, Zhengang
    Wen, Qinglong
    Yuan, Bo
    He, Liang
    Gao, Shixin
    Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 : 175 - 180
  • [3] Experimental Study on Pool Boiling Heat Transfer of Cr-coated Zirconium Cladding
    Zeng X.
    Chen Z.
    Wen Q.
    Du Q.
    Zhang R.
    Du P.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (02): : 91 - 97
  • [4] Current progress of Cr-coated zirconium alloy cladding for accident tolerant fuel
    Duan Z.
    Chen P.
    Zhou Y.
    Gao S.
    Jiao Y.
    Yin C.
    He L.
    He Jishu/Nuclear Techniques, 2022, 45 (03):
  • [5] EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS
    Cervenka, Petr
    Krejci, Jakub
    Cvrcek, Ladislav
    Rozkosny, Vojtech
    Manoch, Frantisek
    Rada, David
    Kabatova, Jitka
    STUDENT CONFERENCE ON NUCLEAR ENGINEERING (SIMANE 2020), 2020, 28 : 1 - 7
  • [6] Effects of internal pressure and heating rate on the burst behaviors of Cr-coated cladding during simulated LOCA testing
    Duan, Zhengang
    Yuan, Bo
    Wen, Qinglong
    Zhang, Ruiqian
    Chen, Kang
    ANNALS OF NUCLEAR ENERGY, 2024, 204
  • [7] Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
    Yook, Hyunwoo
    Shirvan, Koroush
    Phillips, Bren
    Lee, Youho
    JOURNAL OF NUCLEAR MATERIALS, 2022, 558
  • [8] Chromium-coated cladding analysis under simulated LOCA burst conditions
    Sweet, Ryan
    Mouche, Peter
    Bell, Samuel
    Kane, Kenneth
    Capps, Nathan
    ANNALS OF NUCLEAR ENERGY, 2022, 176
  • [9] INVESTIGATION ON OXIDATION BEHAVIORS OF FECRAL ALLOY CLADDING UNDER THE SIMULATED LOCA CONDITIONS
    Chen, Kang
    Du, Zhengang
    Wen, Qinglong
    Zhang, Ruiqian
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, ICONE31 2024, 2024,
  • [10] Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing
    Bell, S. B.
    Graening, T.
    Evans, A.
    Kelly, P.
    Pint, B. A.
    Kane, K. A.
    JOURNAL OF NUCLEAR MATERIALS, 2022, 564
12345