THERMOMIGRATION OF OXYGEN IN (U,PU)O2-X DESCRIBED BY A CLUSTER MODEL

被引:8
作者
NORRIS, DIR [1 ]
机构
[1] CENT ELECT GENERATING BOARD,BERKELEY NUCL LABS,BERKELEY GL13 9PB,GLOUCESTERSHIRE,ENGLAND
关键词
D O I
10.1016/0022-3115(77)90211-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
引用
收藏
页码:13 / 18
页数:6
相关论文
共 19 条
[1]   THERMAL DIFFUSION IN CLOSED OXIDE FUEL SYSTEMS [J].
AITKEN, EA .
JOURNAL OF NUCLEAR MATERIALS, 1969, 30 (1-2) :62-&
[2]   REDISTRIBUTION OF PLUTONIUM AND URANIUM IN MIXED (U, PU) OXIDE FUEL MATERIALS IN A THERMAL GRADIENT [J].
BOBER, M ;
SARI, C ;
SCHUMACHER, G .
JOURNAL OF NUCLEAR MATERIALS, 1971, 39 (03) :265-+
[3]  
Bober M., 1973, ADV NUCL SCI TECHNOL, V7, P121
[4]   MEASUREMENT OF RESISTIVITY AND KINETICS OF OXIDATION IN PUO(2-X) [J].
CHEREAU, P ;
WADIER, JF .
JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (01) :1-8
[5]  
CHRISTENSEN JA, 1967, BNWL536 REP
[6]   EFFECT OF A TEMPERATURE GRADIENT ON STOICHIOMETRY OF URANIA-PLUTONIA FUEL [J].
EVANS, SK ;
AITKEN, EA ;
CRAIG, CN .
JOURNAL OF NUCLEAR MATERIALS, 1969, 30 (1-2) :57-&
[7]  
EVANS SK, 1975, GEAP14036 GEN EL REP
[8]   HEAVY ISOTOPE IN A SOLID DRIFTS DOWN A THERMAL ENERGY GRADIENT [J].
HESKETH, RV .
JOURNAL DE PHYSIQUE, 1976, 37 (03) :183-188
[9]  
HESKETH RV, IN PRESS
[10]  
HESKETH RV, 1971, ATOMIC TRANSPORT SOL, P23