Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

Citation
Mj. Jhung et al., Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams, INT J PRES, 76(12), 1999, pp. 813-823
Citations number
8
Categorie Soggetti
Mechanical Engineering
Journal title
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
ISSN journal
03080161 → ACNP
Volume
76
Issue
12
Year of publication
1999
Pages
813 - 823
Database
ISI
SICI code
0308-0161(199910)76:12<813:PTSAOA>2.0.ZU;2-J
Abstract
Evaluated in this study is the pressure vessel integrity under a pressurize d thermal shock. Using transient histories such as temperature, pressure an d heat transfer coefficient, the stress distribution is calculated and then stress intensity factors are obtained for a wide range of crack sizes. The stress intensity factors are compared with the fracture toughness to check if cracking is expected to occur during the transient. Critical crack dept h diagrams are prepared for each transient which is expected to initiate a pressurized thermal shock accident. Plant-specific analyses of the most lim iting plant in Korea are performed to assure the structural integrity of th e reactor vessel and the results are discussed. (C) 1999 Elsevier Science L td. All rights reserved.