POSSIBLE MECHANISM FOR CORROSION PRODUCT TRANSPORT AND RADIATION-FIELD GROWTH IN A PRESSURIZED WATER-REACTOR PRIMARY CIRCUIT

被引:15
作者
BURRILL, KA [1 ]
机构
[1] ATOM ENERGY CANADA LTD,CHALK RIVER NUCL LABS,CHALK RIVER K0J 1J0,ONTARIO,CANADA
关键词
D O I
10.13182/NT77-A31962
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:85 / 92
页数:8
相关论文
共 7 条
[1]  
BURRILL KA, 1977, CAN J CHEM ENG, V55, P54, DOI 10.1002/cjce.5450550110
[2]  
COHEN P, 1969, WATER COOLANT TECHNO, P49
[3]   TRANSPORT OF RADIOACTIVE CORROSION PRODUCTS IN HIGH-TEMPERATURE WATER .2. ACTIVATION OF ISOTHERMAL STEEL SURFACES [J].
LISTER, DH .
NUCLEAR SCIENCE AND ENGINEERING, 1976, 59 (04) :406-426
[4]  
MEEK ME, 1965, WCAP326951 WEST EL C
[5]  
SAWOCHKA SG, 1975, EPRI4042 EL POW RES
[6]   MEASUREMENT OF FUEL-ELEMENT CRUD DEPOSITS IN PRESSURIZED WATER REACTORS [J].
SOLOMON, Y ;
ROESMER, J .
NUCLEAR TECHNOLOGY, 1976, 29 (02) :166-173
[7]  
Sweeton F.H., 1970, J CHEM THERMODYN, V2, P479, DOI DOI 10.1016/0021-9614(70)90098-4