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
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.