BEHAVIOR OF MIXED OXIDE (U,PU)O2 FUELS AS A FUNCTION OF TEMPERATURE AND BURNUP

被引：3
|
作者：
CARROLL, RM
SISMAN, O
机构：
来源：
NUCLEAR TECHNOLOGY | 1971年 / 11卷 / 04期
关键词：
D O I：
10.13182/NT71-A30855
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
引用
收藏
页码：578 / &
相关论文
共 50 条
  • [1] THERMODYNAMIC BEHAVIOR OF (U, PU) MIXED-OXIDE FUELS
    JAVED, NA
    JOURNAL OF NUCLEAR MATERIALS, 1973, 47 (03) : 336 - 344
  • [2] GAS RELEASE BY (U,PU)O2 FUELS
    PECHIN, WH
    BRADLEY, RA
    SEASE, JD
    AMERICAN CERAMIC SOCIETY BULLETIN, 1971, 50 (04): : 425 - &
  • [3] Melting behavior of (Th,U)O2 and (Th,Pu)O2 mixed oxides
    Ghosh, P. S.
    Kuganathan, N.
    Galvin, C. O. T.
    Arya, A.
    Dey, G. K.
    Dutta, B. K.
    Grimes, R. W.
    JOURNAL OF NUCLEAR MATERIALS, 2016, 479 : 112 - 122
  • [4] Thermodynamic modelling of the (U, Pu, Np)O2±x mixed oxide
    Hirota, M
    Kurosaki, K
    Setoyama, D
    Kato, M
    Osaka, M
    Narnekawa, T
    Uno, M
    Yamanaka, S
    JOURNAL OF NUCLEAR MATERIALS, 2005, 344 (1-3) : 84 - 88
  • [5] Modelling of plutonium diffusion in (U,Pu)O2±x mixed oxide
    Chakraborty, P.
    Gueneau, C.
    Chartier, A.
    SOLID STATE IONICS, 2020, 357
  • [6] IN-PILE CREEP STUDY ON MIXED-OXIDE (U,PU)O2
    COMBETTE, P
    MILET, C
    TANIS, G
    CROUZET, J
    MASSON, M
    JOURNAL OF NUCLEAR MATERIALS, 1977, 65 (01) : 37 - 47
  • [7] LOW-BURNUP IRRADIATION TESTS OF SPHERE-PAC SOL-GEL (U,PU)O2 FUELS
    OLSEN, AR
    COX, CM
    FITTS, RB
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (02): : 605 - &
  • [8] PLUTONIUM DISTRIBUTION IN MELTED (U, PU)O2 NUCLEAR FUELS
    MUHLING, G
    STOLL, W
    THEISEN, R
    JOURNAL OF NUCLEAR MATERIALS, 1967, 24 (03) : 323 - &
  • [9] Using molecular dynamics to predict the solidus and liquidus of mixed oxides (Th, U)O2, (Th, Pu)O2 and (Pu, U)O2
    Galvin, C. O. T.
    Burr, P. A.
    Cooper, M. W. D.
    Fossati, P. C. M.
    Grimes, R. W.
    JOURNAL OF NUCLEAR MATERIALS, 2020, 534
  • [10] Effect of spent fuel burnup and composition on alteration of the U(Pu)O2 matrix
    Jégou, C
    Peuget, S
    Lucchini, JF
    Corbel, C
    Broudic, V
    Bart, JM
    SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXIV, 2000, 663 : 399 - 408
12345