ANALYSIS OF COOLANT BEHAVIOR FOLLOWING FUEL FAILURE AND MOLTEN FUEL-SODIUM INTERACTION IN A FAST NUCLEAR-REACTOR

被引：12
作者：
CRONENBERG, AW [1 ]
FAUSKE, HK [1 ]
EGGEN, DT [1 ]
机构：
[1] ARGONNE NATL LAB, ARGONNE, IL 60439 USA
来源：
NUCLEAR SCIENCE AND ENGINEERING | 1973年 / 50卷 / 01期
关键词：
D O I：
10.13182/NSE73-A22588
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：53 / 62
页数：10
相关论文
共 50 条
[21]   Numerical Heat Transfer Analysis of Solidification of Nuclear Material Droplets during Molten Fuel Coolant Interaction [J].
Poojitha, G. Sri ;
Sudha, A. Jasmin ;
Ponraju, D. .
RENEWABLE ENERGY SOURCES AND TECHNOLOGIES, 2019, 2161
[22]   SODIUM-LOGGING BEHAVIOR OF FAST OXIDE REACTOR FUEL [J].
ONEILL, GL ;
JOHNSON, ML ;
NOVAK, PE .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1964, 7 (01) :107-&
[23]   CONSIDERATIONS OF SODIUM CONDITIONS AND MOLTEN-FUEL/SODIUM INTERACTIONS FOR FAST REACTOR EXCURSION CALCULATIONS [J].
WALTAR, AE ;
HARRIS, RA ;
PADILLA, A .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02) :694-&
[24]   FUEL PIN FAILURE PROPAGATION IN A SODIUM COOLED FAST-REACTOR [J].
JUDD, AM .
JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1973, 12 (01) :35-42
[25]   APPLICATION OF ADJOINT SENSITIVITY ANALYSIS TO NUCLEAR-REACTOR FUEL-ROD PERFORMANCE [J].
WILDERMAN, SJ ;
WAS, GS .
NUCLEAR ENGINEERING AND DESIGN, 1984, 80 (01) :27-38
[26]   ALUMINUM URANIUM FUEL-MELT BEHAVIOR DURING SEVERE NUCLEAR-REACTOR ACCIDENTS [J].
ELLISON, PG ;
HYDER, ML ;
MONSON, PR ;
DEWALD, AB ;
LONG, TA ;
EPSTEIN, M .
NUCLEAR SAFETY, 1993, 34 (02) :196-212
[27]   NUMERICAL-MODEL OF REACTOR-FUEL AND COOLANT MOTIONS FOLLOWING PIN FAILURE [J].
PIZZICA, PA ;
ABRAMSON, PB .
NUCLEAR SCIENCE AND ENGINEERING, 1977, 64 (02) :465-479
[28]   ACCIDENT MITIGATION FROM MOLTEN FUEL/COOLANT DYNAMICS DURING A FAST-REACTOR OVERPOWER EXCURSION [J].
PARTAIN, WL ;
WALTAR, AE .
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 16 (JUN) :189-190
[29]   EXPERIMENTAL TESTS ON APPLICABILITY OF A RADIOACTIVE-TRACER TECHNIQUE FOR MEASURING COOLANT MIXING IN NUCLEAR-REACTOR FUEL SUBASSEMBLIES [J].
CASTELLANI, F ;
CURZIO, G ;
PIEVE, L ;
GRAZZINI, R .
NUCLEAR ENGINEERING AND DESIGN, 1975, 32 (01) :105-109
[30]   Criticality safety analysis of nuclear fuel storage of molten salt reactor [J].
Zhen, Yang ;
Zhimin, Dai ;
Zhangzhong, Yang ;
Yang, Zou .
He Jishu/Nuclear Techniques, 2024, 47 (08)
12345