Modeling of Zr alloy burst cladding internal oxidation and secondary hydriding under LOCA conditions

被引:10
|
作者
Veshchunov, M. S. [1 ,2 ]
Shestak, V. E. [1 ]
机构
[1] Russian Acad Sci, Nucl Safety Inst IBRAE, Moscow 115191, Russia
[2] Moscow Inst Phys & Technol MIPT, Dolgoprudnyi 141700, Moscow Region, Russia
关键词
ZIRCONIUM ALLOYS; HYDROGEN ABSORPTION; STEAM OXIDATION; RELEASE; KINETICS;
D O I
10.1016/j.jnucmat.2015.03.006
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The recently developed mechanistic model for Zr alloy cladding hydriding has been implemented in the single-rod SVECHA/QUENCH (S/Q) code. The mass transfer in a fuel rod after ballooning and burst opening have been modeled in the modified code that allowed calculating hydrogen and oxygen pickup by the cladding inner-metal surface. The code predicts with a good accuracy the typical distributions of oxygen and hydrogen in the Zr alloy cladding that were observed in the JAERI (Japan Atomic Energy Research Institute) and ANL (Argonne National Laboratory) single-rod tests and KIT (Karlsruhe Institute of Technology) bundle tests under postulated loss-of-coolant accident (LOCA) conditions. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:129 / 142
页数:14
相关论文
共 50 条
  • [1] HIGH TEMPERATURE OXIDATION OF NB-CONTAINING ZR ALLOY CLADDING IN LOCA CONDITIONS
    Chuto, Toshinori
    Nagase, Fumihisa
    Fuketa, Toyoshi
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (02) : 163 - 170
  • [2] DLI-MOCVD CrxCy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions
    Brachet, J. C.
    Urvoy, S.
    Rouesne, E.
    Nony, G.
    Dumerval, M.
    Le Saux, M.
    Ott, F.
    Michau, A.
    Schuster, F.
    Maury, F.
    JOURNAL OF NUCLEAR MATERIALS, 2021, 550
  • [3] PRELIMINARY INVESTIGATION ON BURST BEHAVIORS OF ZR-BASED CLADDING UNDER SIMULATED LOCA CONDITIONS
    Duan, Zhengang
    Yuan, Bo
    Wen, Qinglong
    Chen, Kang
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, ICONE31 2024, 2024,
  • [4] 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,
  • [5] PROPERTIES OF ZR ALLOY CLADDING AFTER SIMULATED LOCA OXIDATION AND WATER QUENCHING
    Kim, Hyun-Gil
    Kim, Il-Hyun
    Jung, Yang-Il
    Park, Jeong-Yong
    Jeong, Yong-Hwan
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2010, 42 (02) : 193 - 202
  • [6] 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
  • [7] DEVELOPMENT OF A BURST CRITERION FOR ZIRCALOY FUEL CLADDING UNDER LOCA CONDITIONS.
    Rosinger, H.E.
    Neitzel, H.J.
    Erbacher, F.J.
    Res Mechanica: International Journal of Structural Mechanics and Materials Science, 1981, 2 (02): : 91 - 107
  • [8] Impact of LWR assembly structural features on cladding burst behavior under LOCA conditions
    Schappel, Danny
    Capps, Nathan
    NUCLEAR ENGINEERING AND DESIGN, 2024, 418
  • [9] Simulation method for secondary hydriding breakage of zirconium alloy cladding
    Ma Y.
    Zhang Z.
    Chen J.
    He Jishu/Nuclear Techniques, 2022, 45 (04):
  • [10] Crack formation in cladding under LOCA quench conditions
    Wu, Hsingtzu
    Udagawa, Yutaka
    Narukawa, Takafumi
    Amaya, Masaki
    NUCLEAR ENGINEERING AND DESIGN, 2016, 303 : 25 - 30