Comparative analysis of pressure vessel integrity for various LOCA conditions

被引:7
作者
Çolak, Ü
Özdere, O
机构
[1] Hacettepe Univ, Dept Nucl Engn, Ankara, Turkey
[2] Turkish Atom Energy Agcy, Nucl Safety Dept, Ankara, Turkey
关键词
Pressurized thermal shocks (PTS);
D O I
10.1016/S0022-3115(01)00641-9
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In this study, integrity analysis is performed for a classical four loop PWR pressure vessel fabricated from SA533B type ferritic steel. Pressure vessel behavior is analyzed by deterministic and probabilistic methods under transient conditions, which may cause pressurized thermal shock (PTS). In deterministic analysis, the change of material properties and the mechanical state of the vessel are analyzed against changes in coolant pressure and temperature. Probabilistic analysis is performed to obtain pressure vessel beltline region weld failure probabilities in transient conditions. Overall vessel failure probabilities are evaluated based on the results of deterministic analyses. Computer code VISA-II is utilized for the calculation of vessel failure probabilities. Among three cases considered in this study, a medium break loss of coolant accident induced by a 50 cm(2) break in the hot leg yields the highest vessel rupture probability. The maximum nil ductility temperature in all cases is still below the NRC PTS limit. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:271 / 278
页数:8
相关论文
共 14 条
[1]  
[Anonymous], 1981, RELIABILITY RISK ANA
[2]   PWR STEEL PRESSURE-VESSEL DESIGN AND PRACTICE [J].
BANGASH, Y .
PROGRESS IN NUCLEAR ENERGY, 1985, 16 (01) :1-40
[3]   Probabilistic assessment of reactor pressure vessel integrity under pressurised thermal shock [J].
Dutta, BK ;
Kushwaha, HS ;
Raj, VV .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1999, 76 (07) :445-453
[4]  
FLETCHER CD, 1992, NUREGCR5535 EGG
[5]  
*INT COMP ASS STUD, 1999, NUREGCR6651
[6]   The effect of flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock [J].
Jang, CH ;
Jeong, IS ;
Hong, SY .
NUCLEAR ENGINEERING AND DESIGN, 2000, 197 (03) :249-264
[7]   Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams [J].
Jhung, MJ ;
Park, YW ;
Jang, CH .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1999, 76 (12) :813-823
[8]   Deterministic assessment of reactor pressure vessel integrity under pressurised thermal shock [J].
Mukhopadhyay, NK ;
Kumar, TVP ;
Chattopadhyay, J ;
Dutta, BK ;
Kushwaha, HS ;
Raj, VV .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1998, 75 (15) :1055-1064
[9]   Microscopic investigation of cleavage initiation in modified A508B pressure vessel steel [J].
Narström, T ;
Isacsson, M .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1999, 271 (1-2) :224-231
[10]  
Pershagen B, 1989, LIGHT WATER REACTOR SAFETY Probabilistic Risk Assessment in the Nuclear Power Industry