GRABB - A COMPUTER CODE FOR SIMULATING FISSION-GAS DISPOSITION IN OXIDE FUEL DURING FAST THERMAL TRANSIENT

被引:2
|
作者
CHIEN, SH [1 ]
WAZZAN, AR [1 ]
OKRENT, D [1 ]
机构
[1] UNIV CALIF LOS ANGELES,SCH ENGN & APPL SCI,DEPT CHEM NUCL & THERMAL ENGN,LOS ANGELES,CA 90024
关键词
D O I
10.13182/NT83-A33103
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:69 / 83
页数:15
相关论文
共 50 条
  • [41] LOCAL FISSION-GAS RELEASE AND SWELLING IN WATER-REACTOR FUEL DURING SLOW POWER TRANSIENTS
    MOGENSEN, M
    WALKER, CT
    RAY, ILF
    COQUERELLE, M
    JOURNAL OF NUCLEAR MATERIALS, 1985, 131 (2-3) : 162 - 171
  • [42] Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS
    Barani, T.
    Bruschi, E.
    Pizzocri, D.
    Pastore, G.
    Van Uffelen, P.
    Williamson, R. L.
    Luzzi, L.
    JOURNAL OF NUCLEAR MATERIALS, 2017, 486 : 96 - 110
  • [43] EFFECT OF SLOW FISSION-GAS DILUTION ON LWR FUEL-ROD BEHAVIOR DURING POWER TRANSIENTS
    NAKAMURA, M
    HIRAMOTO, K
    MARU, A
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 46 : 340 - 341
  • [44] ISUNE 1 - A COMPUTER CODE FOR PERFORMING RADIATION, THERMAL, AND MECHANICAL ANALYSIS OF OXIDE FUEL PINS OF FAST REACTORS
    MA, BM
    CHENG, CK
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 125 - &
  • [45] FISSION-GAS AND CESIUM GRADIENTS IN SINGLE GRAINS OF TRANSIENT TESTED UO2 FUEL - RESULTS OF AN EPMA INVESTIGATION
    WALKER, CT
    LASSMANN, K
    JOURNAL OF NUCLEAR MATERIALS, 1986, 138 (2-3) : 155 - 161
  • [46] IMPACT OF FUEL HETEROGENEITIES ON FISSION-GAS RELEASE FOR LWR U-PU MIXED-OXIDE FUELS
    BILLAUX, M
    VANVLIET, J
    RES MECHANICA, 1986, 17 (01): : 41 - 57
  • [47] EVALUATION OF THE FISSION-GAS RELEASE BEHAVIOR FROM FAST-REACTOR MIXED-OXIDE FUEL BASED ON LOCAL CONCENTRATION MEASUREMENT OF RETAINED XENON
    UKAI, S
    HOSOKAWA, T
    SHIBAHARA, I
    ENOKIDO, Y
    JOURNAL OF NUCLEAR MATERIALS, 1988, 151 (02) : 209 - 218
  • [48] FISSION GAS BEHAVIOR IN FAST-REACTOR FUEL UNDER TRANSIENT POWER CONDITIONS
    DIAS, JW
    ERDMANN, RC
    OKRENT, D
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 358 - 359
  • [49] FISSION GAS BEHAVIOR IN FAST-REACTOR FUEL UNDER TRANSIENT POWER CONDITIONS
    DIAS, JW
    OKRENT, D
    ERDMANN, RC
    NUCLEAR TECHNOLOGY, 1974, 24 (01) : 20 - 32
  • [50] Coupled computer code study on irradiation performance of a fast reactor mixed oxide fuel element with an emphasis on the fission product cesium behavior
    Uwaba, Tomoyuki
    Nemoto, Junichi
    Ishitani, Ikuo
    Ito, Masahiro
    NUCLEAR ENGINEERING AND DESIGN, 2018, 331 : 186 - 193