SOME RESEARCH WORKS ON WORKING OUT OF A PROTOTYPE OF AN ONE-FLOW-STEAM GENERATOR FOR NUCLEAR-POWER PLANT WITH PRESSURIZED WATER-REACTOR

被引：0

|

作者：

GAJEWSKI, W

JEDRZEJEWSKI, R

机构：

来源：

NUKLEONIKA | 1978年 / 23卷 / 6-7期

关键词：

D O I：

暂无

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

引用

收藏

页码：553 / 571

页数：19

相关论文

共 47 条

[41] THERMAL-HYDRAULIC CHARACTERISTICS OF PRESSURIZED WATER-REACTORS DURING COMMERCIAL OPERATION .1. CIRCULATION RATIO AND CARRY-UNDER IN A PWR STEAM-GENERATOR (BUGEY-4 NUCLEAR-POWER PLANT)
WAZZAN, AR
PROCACCIA, H
DAVID, J
DEPENGUERN, L
HAMON, P
NUCLEAR ENGINEERING AND DESIGN, 1982, 70 (02) : 145 - 158
[42] THERMAL HYDRAULIC CHARACTERISTICS OF PRESSURIZED WATER-REACTORS DURING COMMERCIAL OPERATION .5. STEADY-STATE THERMAL MEASUREMENTS ON THE SECONDARY SIDE OF A PWR STEAM-GENERATOR (TRICASTIN-1 NUCLEAR-POWER PLANT)
PROCACCIA, H
DAVID, J
WAZZAN, AR
NUCLEAR ENGINEERING AND DESIGN, 1984, 80 (01) : 87 - &
[43] THERMAL HYDRAULIC CHARACTERISTICS OF PRESSURIZED WATER-REACTORS DURING COMMERCIAL OPERATION .4. SATURATION PRESSURE, CIRCULATION RATIO AND CARRY-UNDER IN A PWR STEAM-GENERATOR (TRICASTIN-1 NUCLEAR-POWER PLANT)
WAZZAN, AR
PROCACCIA, H
DAVID, J
NUCLEAR ENGINEERING AND DESIGN, 1984, 80 (01) : 79 - 86
[44] THERMAL-HYDRAULIC CHARACTERISTICS OF PRESSURIZED WATER-REACTORS DURING COMMERCIAL OPERATION .2. STEADY-STATE THERMAL MEASUREMENTS ON THE SECONDARY SIDE OF A PWR STEAM-GENERATOR (BUGEY-4 NUCLEAR-POWER PLANT)
PROCACCIA, H
DAVID, J
DEPENGUERN, L
WAZZAN, AR
NUCLEAR ENGINEERING AND DESIGN, 1982, 70 (02) : 159 - 171
[45] EXPERIMENTAL INVESTIGATION OF CHANGES IN COOLANT FLOW-RATE THROUGH THE CORE IN THE CASE OF COOLANT PUMP FAILURE AND COMPARISON WITH RESULTS OF THEORETICAL INVESTIGATIONS ON A NUCLEAR-POWER PLANT WITH WWER-440 TYPE PRESSURIZED-WATER REACTOR
BARTOLOMEJ, GG
MERTINS, M
ZIMMER, E
KERNENERGIE, 1980, 23 (01): : 12 - 15
[46] ARGOS PHWR-380 - ARGENTINE OFFER OF A SAFER PRESSURIZED HEAVY-WATER REACTOR OF 380 MW ... A MANY-EYED GUARDIAN ... CONCERNED ABOUT NUCLEAR-POWER PLANT SAFETY
GONZALEZ, AJ
FRISCHENGRUBER, K
RECALDE, JA
SOLANILLA, RB
VANZULLI, RC
NUCLEAR ENGINEERING AND DESIGN, 1988, 109 (1-2) : 55 - 64
[47] THERMAL-HYDRAULIC CHARACTERISTICS OF PRESSURIZED WATER-REACTORS DURING COMMERCIAL OPERATION .3. PWR STEAM-GENERATOR RESPONSE TO A SCRAM AT 50-PERCENT LOAD AND AN OPEN GRID TRANSIENT (BUGEY-4 NUCLEAR-POWER PLANT)
DEPENGUERN, L
DAVID, J
PROCACCIA, H
WAZZAN, AR
NUCLEAR ENGINEERING AND DESIGN, 1982, 70 (02) : 173 - 186

← 1 2 3 4 5 →