STUDY OF RETENTION OF BA IN UO2 NUCLEAR-FUEL PARTICLES BY ZRO2 AS GETTER

被引：3
|
作者：
ODOJ, R
HILPERT, K
NURNBERG, HW
FORTHMANN, R
NAOUMIDIS, A
机构：
[1] KFA,NUCL RES CTR,INST CHEM,JULICH,FED REP GER
[2] KFA,NUCL RES CTR,INST REACTOR MAT,JULICH,FED REP GER
[3] KFA,NUCL RES CTR,INST APPL PHYS CHEM,JULICH,FED REP GER
来源：
JOURNAL OF NUCLEAR MATERIALS | 1976年 / 60卷 / 02期
关键词：
D O I：
10.1016/0022-3115(76)90168-9
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
引用
收藏
页码：216 / 222
页数：7
相关论文
共 50 条
  • [31] Oxidative dissolution of Cr-doped UO2 nuclear fuel
    Smith, Hannah
    Cordara, Theo
    Gausse, Clemence
    Pepper, Sarah E.
    Corkhill, Claire L.
    NPJ MATERIALS DEGRADATION, 2023, 7 (01)
  • [32] Modelling of stable fission gases diffusion in UO2 nuclear fuel
    Vallejo, I.
    Herranz, L. E.
    DIFFUSION IN SOLIDS AND LIQUIDS III, 2008, 273-276 : 693 - 698
  • [33] CRITICAL CONCENTRATION FOR MAGNETIC ORDER IN SOLID-SOLUTIONS OF UO2 WITH THO2 AND ZRO2
    SABINE, TM
    SMITH, GB
    REEVE, KD
    JOURNAL OF PHYSICS C-SOLID STATE PHYSICS, 1974, 7 (24): : 4513 - 4521
  • [34] DIRECT RECOVERY OF UO2 SCRAP POWDERS AND THEIR INFLUENCE ON THE QUALITY OF THE UO2 FUEL
    HENKE, M
    KERNENERGIE, 1985, 28 (08): : 348 - 351
  • [35] Flash sintering of UO2 pellets for nuclear fuel and wasteform applications
    Harrison, R. W.
    Morgan, J.
    Buckley, J.
    Bostanchi, S.
    Pearmain, D.
    Abram, T.
    Goddard, D.
    Barron, N.
    JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2025, 45 (03)
  • [36] DENSIFICATION IN IRRADIATED UO2 FUEL
    HASTINGS, IJ
    FEHRENBACH, PJ
    HOSBONS, RR
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1984, 67 (02) : C24 - C25
  • [37] Oxidative dissolution of Cr-doped UO2 nuclear fuel
    Hannah Smith
    Théo Cordara
    Clémence Gausse
    Sarah E. Pepper
    Claire L. Corkhill
    npj Materials Degradation, 7
  • [38] UO2 FUEL FABRICATION DEVELOPMENT
    FERRARI, S
    GIAQUINT.L
    MORETTI, S
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02): : 486 - &
  • [39] Fission product speciation across a UO2 spent nuclear fuel
    Klosek, V.
    Hunault, M. O. J. Y.
    Schlutig, S.
    Tomczak, W.
    Rochedy, M.
    Solari, P. L.
    Noirot, J.
    JOURNAL OF NUCLEAR MATERIALS, 2023, 586
  • [40] Fission gas release from UO2 nuclear fuel: A review
    Rest, J.
    Cooper, M. W. D.
    Spino, J.
    Turnbull, J. A.
    Van Uffelen, P.
    Walker, C. T.
    JOURNAL OF NUCLEAR MATERIALS, 2019, 513 : 310 - 345
12345