Investigation　on　two－phase　critical　flow　for　loss－of－coolant　accident　of　pressurized　water　reactor

被引：0

作者：

徐进良

陈听宽

李鲁伟

机构：

来源：

Nuclear Science and Techniques | 1996年 / 03期

关键词：

Critical flow; System transition characteristic; Wall surface cavity nucleation model; Pressurized water reactor;

D O I：

暂无

中图分类号：

O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Ｉｎｖｅｓｔｉｇａｔｉｏｎｏｎｔｗｏ－ｐｈａｓｅｃｒｉｔｉｃａｌｆｌｏｗｆｏｒｌｏｓｓ－ｏｆ－ｃｏｏｌａｎｔａｃｃｉｄｅｎｔｏｆｐｒｅｓｓｕｒｉｚｅｄ　ｗａｔｅｒ　ｒｅａｃｔｏｒＸｕＪｉｎ－Ｌｉａｎｇ（徐进良）（ＩｎｓｔｉｔｕｔｅｏｆＮｕｃｌｅａｒＥ...

引用

页码：143 / 150

页数：8

共 50 条

[1] THE REFLOODING PHASE AFTER A LOSS-OF-COOLANT ACCIDENT IN AN ADVANCED PRESSURIZED WATER-REACTOR
CIGARINI, M
DONNE, MD
NUCLEAR TECHNOLOGY, 1989, 84 (01) : 33 - 53
[2] COOLANT RECIRCULATION IN A PRESSURIZED WATER-REACTOR CORE UNDER LOSS-OF-COOLANT ACCIDENT CONDITIONS
MOALLEMI, MK
VISKANTA, R
NUCLEAR SCIENCE AND ENGINEERING, 1988, 98 (03) : 209 - 225
[3] LOSS-OF-COOLANT ACCIDENT ANALYSIS IN PRESSURIZED WATER REACTORS
NAHAVANDI, AN
NUCLEAR SCIENCE AND ENGINEERING, 1969, 36 (02) : 159 - +
[4] INVESTIGATION OF CRITICAL FLOW CONDITION DURING A LOSS-OF-COOLANT ACCIDENT
CURET, HD
SHIBA, M
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (02): : 879 - &
[5] Experimental investigation on 1% small break loss-of-coolant accident of pressurized water reactor cold leg
Zhou, Runbin
Li, Fengchen
Xu, Guohua
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[6] PUMP BEHAVIOR AND ITS IMPACT ON A LOSS-OF-COOLANT ACCIDENT IN A PRESSURIZED WATER-REACTOR
KASTNER, W
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NUCLEAR TECHNOLOGY, 1983, 60 (02) : 268 - 277
[7] Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor
Dehjourian, Mehdi
Sayareh, Reza
Rahgoshay, Mohammad
Jahanfarnia, Gholamreza
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NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (05) : 1174 - 1183
[8] RESEARCH OF THE INFLUENCE OF A LOSS-OF-COOLANT ACCIDENT ON THE INTERNAL STRUCTURES OF A PRESSURIZED WATER-REACTOR
HAVELKA, Z
SUCHANEK, M
JADERNA ENERGIE, 1984, 30 (07): : 264 - 267
[9] NUMERICAL SIMULATION OF THE TRANSIENT PHASE CHANGE HEAT TRANSFER IN A PRESSURIZED WATER REACTOR CORE DURING A LOSS-OF-COOLANT ACCIDENT
Jo, Soo W.
Lee, Yong K.
Jo, Jong C.
PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 2: COMPUTER TECHNOLOGY AND BOLTED JOINTS, 2012, : 335 - 341
[10] REACTOR HYDRODYNAMICS DURING REFLOOD PHASE OF A LOSS-OF-COOLANT ACCIDENT
GAY, RR
NUCLEAR TECHNOLOGY, 1977, 36 (02) : 229 - 237

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Investigation on two－phase critical flow for loss－of－coolant accident of pressurized water reactor

Investigation　on　two－phase　critical　flow　for　loss－of－coolant　accident　of　pressurized　water　reactor