MEA SEMINAR ON EXPERIENCE GAINED WITH DESIGN AND DURING OPERATION OF FAST-REACTOR STEAM-GENERATORS

被引：0

作者：

PRIDOHL, E

机构：

来源：

KERNENERGIE | 1982年 / 25卷 / 12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

页码：487 / 488

页数：2

共 43 条

[1] THE PROTOTYPE FAST-REACTOR, STEAM-GENERATORS
BARCLAY, FJ
[J]. NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1995, 34 (01): : 10 - 10
[2] THE PROTOTYPE FAST-REACTOR, STEAM-GENERATORS - REPLY
BARCLAY, FJ
[J]. NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1995, 34 (02): : 71 - 71
[3] OPERATION OF PROTOTYPE FAST-REACTOR STEAM-GENERATORS LED DIRECTLY TO COMMERCIAL-SIZE DESIGN
TAYLOR, D
[J]. NUCLEAR ENGINEERING INTERNATIONAL, 1977, 22 (257): : 49 - 53
[4] IAEA CONFERENCE ON LEAK DETECTION IN FAST-REACTOR STEAM-GENERATORS
MAVRIN, AS
[J]. SOVIET ATOMIC ENERGY, 1979, 46 (01): : 72 - 73
[5] FERRITIC STEELS FOR FAST-REACTOR STEAM-GENERATORS - CRITICAL-ASSESSMENT
PUGH, SF
LITTLE, EA
[J]. NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1978, 17 (03): : 179 - 183
[6] MAIN DEVELOPMENT DIRECTIONS OF THE SODIUM COOLED FAST-REACTOR STEAM-GENERATORS
KRIZEK, V
[J]. JADERNA ENERGIE, 1979, 25 (09): : 321 - 331
[7] SEMINAR ON STEAM-GENERATORS FOR FAST-REACTORS
LUKASEVICH, BI
[J]. SOVIET ATOMIC ENERGY, 1979, 46 (06): : 487 - 488
[8] SELECTION OF VALUES OF DESIGN PEAK HEAT-FLUX TO REDUCE RISK OF WATERSIDE CORROSION IN FAST-REACTOR STEAM-GENERATORS
BOLT, PR
GARNSEY, R
[J]. JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1976, 15 (02): : 157 - 161
[9] EXPERIENCE WITH LIQUID-METAL FAST BREEDER REACTOR STEAM-GENERATORS UNITED-STATES DESIGN
STONE, CC
FORD, JA
TIPPETS, FE
MCDONALD, JS
GRANT, G
EPSTEIN, JL
[J]. NUCLEAR TECHNOLOGY, 1981, 55 (01) : 60 - 87
[10] EXPERIENCE IN OPERATING GAS-COOLED REACTOR STEAM-GENERATORS OF UK DESIGN
JAMES, DW
[J]. NUCLEAR TECHNOLOGY, 1981, 55 (01) : 50 - 59

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