PERFORMANCE OF MIXED-OXIDE FUEL ELEMENTS WITH CENTER MELTING

被引：0
|
作者：
BROWN, FL
NEIMARK, LA
MURPHY, WF
NATESH, R
机构：
来源：
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY | 1969年 / 12卷 / 01期
关键词：
D O I：
暂无
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：107 / &
相关论文
共 50 条
  • [1] PERFORMANCE OF MIXED-OXIDE FUEL-ELEMENTS - ANL EXPERIENCE
    NEIMARK, LA
    DICKERMAN, CE
    LAMBERT, JDB
    MURPHY, WF
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (NAPR): : 22 - +
  • [2] TRANSIENT PERFORMANCE OF MIXED-OXIDE POWDER FUEL WITH UP TO 60 PERCENT MELTING
    THOMAS, GR
    FIELD, JH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (01): : 343 - &
  • [3] FAILURE MECHANISM IN MIXED-OXIDE FUEL-ELEMENTS
    LAMBERT, JDB
    NEIMARK, LA
    STRAIN, RV
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 17 (NOV): : 193 - 194
  • [4] EVALUATION OF THE MIXED-OXIDE FUEL MELTING LIMIT AT LOW BURNUPS
    KOMODA, S
    HOSOKAWA, T
    KINJO, K
    KERNTECHNIK, 1990, 55 (02) : 112 - 116
  • [5] Mixed-oxide (MOX) fuel performance benchmarks
    Ott, L. J.
    Tverberg, Terje
    Sartori, Enrico
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (03) : 375 - 379
  • [6] THERMAL REACTOR MIXED-OXIDE FUEL PERFORMANCE
    FRESHLEY, MD
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (02): : 563 - &
  • [7] PERFORMANCE ANALYSIS OF MIXED-OXIDE FUEL PINS
    NAYAK, UP
    BOLTAX, A
    BIANCHERIA, A
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1974, 19 (OCT27): : 115 - 116
  • [8] CHEMICAL ATTACK OF CLADDING IN MIXED-OXIDE FUEL-ELEMENTS
    JOHNSON, CE
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 153 - 154
  • [9] EFFECT OF EXPOSURE TO SODIUM OF DEFECTED MIXED-OXIDE FUEL ELEMENTS
    GREENBER.S
    RUTHER, WE
    HONEKAMP, JR
    DONAHUE, DA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1971, 14 (01): : 178 - &
  • [10] MELTING TEMPERATURE AND THERMAL-CONDUCTIVITY OF IRRADIATED MIXED-OXIDE FUEL
    YAMAMOTO, K
    HIROSAWA, T
    YOSHIKAWA, K
    MOROZUMI, K
    NOMURA, S
    JOURNAL OF NUCLEAR MATERIALS, 1993, 204 : 85 - 92
12345