CORROSION PRODUCT TRANSPORT IN WATER-COOLED NUCLEAR-REACTORS .1. PRESSURIZED WATER OPERATION

被引：0

作者：

BURRILL, KA ^{[1
]}

机构：

[1] ATOM ENERGY CANADA LTD,CHALK RIVER NUCL LABS,SYST MAT BRANCH,CHALK RIVER K0J 1J0,ONTARIO,CANADA

来源：

CANADIAN JOURNAL OF CHEMICAL ENGINEERING | 1977年 / 55卷 / 01期

关键词：

D O I：

暂无

中图分类号：

TQ [化学工业];

学科分类号：

0817 ;

摘要：

引用

页码：54 / 61

页数：8

共 50 条

[1] CORROSION PRODUCT TRANSPORT IN WATER-COOLED NUCLEAR-REACTORS .3. BOILING WATER WITH INDIRECT CYCLE OPERATION
BURRILL, KA
[J]. CANADIAN JOURNAL OF CHEMICAL ENGINEERING, 1979, 57 (02): : 211 - 224
[2] CORROSION PRODUCT TRANSPORT IN WATER-COOLED NUCLEAR-REACTORS .2. BOILING WATER WITH DIRECT CYCLE OPERATION
BURRILL, KA
[J]. CANADIAN JOURNAL OF CHEMICAL ENGINEERING, 1978, 56 (01): : 79 - 86
[3] TRENDS OF USING AND TESTING MATERIALS IN WATER-COOLED NUCLEAR-REACTORS
BERGEMANN, W
[J]. NEUE HUTTE, 1978, 23 (12): : 437 - 439
[4] FRETTING CORROSION PROBLEM IN WATER COOLED NUCLEAR-REACTORS
GADDA, F
RONCHETTI, C
[J]. ENERGIA NUCLEARE, 1977, 24 (06): : 297 - 305
[5] INTERGRANULAR STRESS-ASSISTED CORROSION CRACKING OF AUSTENITIC ALLOYS IN WATER-COOLED NUCLEAR-REACTORS
CHENG, CF
[J]. JOURNAL OF NUCLEAR MATERIALS, 1975, 57 (01) : 11 - 33
[6] HEAT-TRANSFER AS LIMITING FACTOR IN WATER-COOLED NUCLEAR-REACTORS
KJAERHEIM, G
[J]. NUCLEAR ENGINEERING AND DESIGN, 1972, 21 (02) : 279 - +
[7] ADVANCES IN WATER-COOLED REACTORS .1. PRESSURISED WATER REACTORS
KELLER, W
[J]. ATOMWIRTSCHAFT, 1970, 15 (9-10): : 469 - &
[8] STEAM-GENERATORS IN INDIRECT CYCLE WATER-COOLED NUCLEAR-REACTORS
FAJEAU, M
[J]. BULLETIN D INFORMATIONS SCIENTIFIQUES ET TECHNIQUES DU COMMISSARIAT A L ENERGIE ATOMIQUE, 1976, (213): : 53 - 61
[9] CORROSION PRODUCT TRANSPORT STUDY IN PRESSURIZED WATER-REACTORS
BESLU, P
FREJAVILLE, G
[J]. TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 31 (MAY): : 129 - 131
[10] HEAT TRANSFER IN WATER-COOLED NUCLEAR REACTORS
TONG, LS
[J]. NUCLEAR ENGINEERING AND DESIGN, 1967, 6 (04) : 301 - &

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