Thermodynamics of chromium in UO2 fuel: A solubility model

被引:40
|
作者
Riglet-Martial, Ch. [1 ]
Martin, Ph. [1 ]
Testemale, D. [2 ,3 ]
Sabathier-Devals, C. [1 ]
Carlot, G. [1 ]
Matheron, P. [1 ]
Iltis, X. [1 ]
Pasquet, U. [1 ]
Valot, C. [1 ]
Delafoy, C. [4 ]
Largenton, R. [5 ]
机构
[1] Commissariat Energie Atom & Energies Alternat, Ctr Etud Cadarache, Dept Etud Combustibles, Direct Energie Nucl, F-13108 St Paul Les Durance, France
[2] Univ Grenoble Alpes, Inst NEEL, F-38042 Grenoble, France
[3] CNRS, Inst NEEL, F-38042 Grenoble, France
[4] AREVA NP SAS, F-69456 Lyon 06, France
[5] EDF R&D, Mech & Mat Component Dept, F-77818 Moret Sur Loing, France
关键词
OXYGEN POTENTIAL MEASUREMENTS; RAY-ABSORPTION SPECTROSCOPY; SYSTEM; CRYSTAL; RELEASE; CR2O3; CR;
D O I
10.1016/j.jnucmat.2013.12.021
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The solubility and speciation of chromium in doped uranium oxide are measured in carefully controlled temperature and oxygen potential conditions using electron probe microanalysis (EPMA) and scanning electron spectroscopy (SEM). The examination of the samples by X-ray Absorption Spectroscopy (XAS) provides evidence that (i) chromium is soluble in the UO2 matrix under the +3 oxidation state only regardless of the sintering conditions which is in accordance with a soluble species of type CrO3/2 and (ii) soluble chromium exhibits octahedral symmetry with 6 atoms of oxygen forming CrO6 patterns in the UO2 structure. In consistency with all available experimental information including previously published data, the solubility of chromium in UO2 corresponding to each two-phase field with either Cr, CrO and Cr2O3 may be described in the ranges 1500 degrees C < T< 2000 degrees C and -460 < mu(O2) < -360 kJ/mol using the standard thermodynamic equations governing solubility equilibria. The characteristic parameters of the solubility laws in UO2 for the three chromium phases are derived. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:63 / 72
页数:10
相关论文
共 50 条
  • [21] VOLUME CHANGES IN IRRADIATED UO2 FUEL
    HASTINGS, IJ
    ROSE, DH
    SCHANKULA, MH
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1975, 58 (1-2) : 74 - 74
  • [22] ECONOMICS OF UO2 FUEL FOR RESEARCH REACTORS
    LUMB, RF
    MACPHEE, J
    NUCLEAR APPLICATIONS, 1967, 3 (03): : 157 - &
  • [23] PREPARATION OF SIMULATED FUEL FRAGMENTS OF UO2
    TINKLE, MC
    KIRCHER, JA
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1981, 181 (MAR): : 15 - NUCL
  • [24] BURNABLE POISON DISPERSION IN UO2 FUEL
    FLIPOT, AJ
    VANDENBR.H
    DELBRASS.A
    GILISSEN, R
    NUCLEAR ENGINEERING INTERNATIONAL, 1970, 15 (167): : 345 - &
  • [25] On the diffusion coefficient of caesium in UO2 fuel
    Lassmann, K
    Schubert, A
    van de Laar, J
    Walker, CT
    FISSION GAS BEHAVIOUR IN WATER REACTOR FUELS, SEMINAR PROCEEDINGS, 2002, : 321 - 334
  • [26] DENSIFICATION ALGORITHM FOR IRRADIATED UO2 FUEL
    HASTINGS, IJ
    EVANS, LE
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1979, 62 (3-4) : 217 - 218
  • [27] An evaluation of the Americium insertion in Uo2 fuel
    Costa, AL
    Pereira, C
    ANNALS OF NUCLEAR ENERGY, 2002, 29 (06) : 767 - 775
  • [28] BEHAVIORS OF MOLYBDENUM IN UO2 FUEL MATRIX
    Ha, Yeong-Keong
    Kim, Jong-Goo
    Park, Yang Soon
    Park, Soon Dal
    Song, Kyuseok
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2011, 43 (03) : 309 - 316
  • [29] OXIDATION BEHAVIOR OF SPENT UO2 FUEL
    CAMPBELL, TK
    GILBERT, ER
    THORNHILL, CK
    WRONA, BJ
    NUCLEAR TECHNOLOGY, 1989, 84 (02) : 182 - 195
  • [30] ENGINEERING FOR FISSION GAS IN UO2 FUEL
    LEWIS, WB
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1965, 8 (01): : 24 - &