Implementation of results from MPA reactor safety research in the integrity assessment of German reactor pressure vessels

Authors
Citation
E. Roos et J. Fohl, Implementation of results from MPA reactor safety research in the integrity assessment of German reactor pressure vessels, NUCL ENG DE, 190(1-2), 1999, pp. 97-115
Citations number
22
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR ENGINEERING AND DESIGN
ISSN journal
00295493 → ACNP
Volume
190
Issue
1-2
Year of publication
1999
Pages
97 - 115
Database
ISI
SICI code
0029-5493(199906)190:1-2<97:IORFMR>2.0.ZU;2-Q
Abstract
The safety analysis of a reactor pressure vessel is performed on a fracture mechanics basis. The paper introduces methods to determine fracture toughn ess values from small scale specimen testing which can be used to predict c rack initiation for large structures even under complex loading conditions. The fracture mechanics concepts were verified for crack initiation and cra ck arrest. Taking the multi-axial stress state into consideration also the amount of stable crack growth could be determined in case of thermal shock loading. It could be confirmed that the fracture mechanics concept of the C ode, based on the reference temperature RTNDT describes the material behavi or conservatively and can be applied to unirradiated as well as irradiated material states. (C) 1999 Elsevier Science S.A. All rights reserved.