Modelling of irradiated UO2 fuel behaviour under transient conditions

被引:24
|
作者
Veshchunov, M. S. [1 ,2 ]
Tarasov, V. I. [1 ]
机构
[1] Russian Acad Sci, Nucl Safety Inst IBRAE, Moscow 115191, Russia
[2] MIPT, Dolgoprudnyi 141700, Russia
关键词
FISSION-GAS BUBBLES; GRAIN-GROWTH KINETICS; RE-SOLUTION; URANIUM-DIOXIDE; NUCLEAR-FUEL; LWR UO2; MIGRATION; EVOLUTION; RELEASE; BURNUP;
D O I
10.1016/j.jnucmat.2013.02.011
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
On the basis of a critical assessment of the Booth-Speight model for the fission gas release from irradiated fuel, a more consistent mechanigtic approach is developed for consideration of the microstructure evolution and fission gas release under conditions of power ramp tests. A new Model that modifies the Nelson model for gas atom resolution from bubbles and explains the observed formation of a new population of large bubbles, is developed and implemented in the MFPR code. Superposition of various mechanisms of gas transport: gas atom diffusion, bubbles random and biased migration, and gas sweeping by grain boundaries, results in a reasonable prediction of the measured fractional gas release and microstructure evolution, observed in the ramp tests. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:250 / 260
页数:11
相关论文
共 50 条
  • [1] Comparison of the leaching behaviour of irradiated fuel, SIMFUEL, and non-irradiated UO2 under oxic conditions
    Serrano, JA
    Rondinella, VV
    Glatz, JP
    Toscano, EH
    Quiñones, J
    Diaz-Arocas, PP
    Garcia-Serrano, J
    RADIOCHIMICA ACTA, 1998, 82 : 33 - 37
  • [2] Modelling and Assessment of Inert Gas Behaviour in UO2 Nuclear Fuel for Transient Analysis
    Pizzocri, Davide
    Luzzi, Lelio
    Pastore, Giovanni
    Van Uffelen, Paul
    27TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2018), 2018,
  • [3] DENSIFICATION IN IRRADIATED UO2 FUEL
    HASTINGS, IJ
    FEHRENBACH, PJ
    HOSBONS, RR
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1984, 67 (02) : C24 - C25
  • [4] Modelling of fission gas release from irradiated UO2 fuel under high-temperature annealing conditions
    Veshchunov, M. S.
    Shestak, V. E.
    JOURNAL OF NUCLEAR MATERIALS, 2012, 430 (1-3) : 82 - 89
  • [5] Modelling of grain face bubbles coalescence in irradiated UO2 fuel
    Veshchunov, M. S.
    JOURNAL OF NUCLEAR MATERIALS, 2008, 374 (1-2) : 44 - 53
  • [6] MIGRATION OF FISSION-PRODUCT BARIUM IN UO2 FUEL UNDER TRANSIENT CONDITIONS
    WALKER, CT
    BAGGER, C
    MOGENSEN, M
    JOURNAL OF NUCLEAR MATERIALS, 1990, 173 (01) : 14 - 25
  • [7] Modelling UO2 and SIMFUEL leaching behaviour in granite groundwater under oxidizing conditions
    Quiñones, J
    Serrano, JG
    Serrano, JA
    Arocas, PD
    Rodriguez, JL
    Blazquez, J
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXII, 1999, 556 : 479 - 485
  • [8] VOLUME CHANGES IN IRRADIATED UO2 FUEL
    HASTINGS, IJ
    ROSE, DH
    SCHANKULA, MH
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1975, 58 (1-2) : 74 - 74
  • [9] DENSIFICATION ALGORITHM FOR IRRADIATED UO2 FUEL
    HASTINGS, IJ
    EVANS, LE
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1979, 62 (3-4) : 217 - 218
  • [10] Fission gas release from UO2 fuel under steady state and transient conditions
    El Koliel, MS
    Szuta, M
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '99, PROCEEDINGS, 1998, : 429 - 432