E. Roos et al., Transferability of results of PTS experiments to the integrity assessment of reactor pressure vessels, NUCL ENG DE, 198(1-2), 2000, pp. 173-183
The integrity assessment of the reactor pressure vessel (RPV) is based on t
he fracture mechanics concept as provided in the code. However, this concep
t covers only the linear-elastic fracture mechanics regime on the basis of
the reference temperature RTNDT as derived from Charpy impact and drop-weig
ht test. The conservatism of this concept was demonstrated for a variety of
different materials covering optimized and lower bound material states wit
h regard to unirradiated and irradiated conditions. For the elastic-plastic
regime, methodologies have been developed to describe ductile crack initia
tion and stable crack growth. Tho transferability of both, the linear-elast
ic and elastic-plastic fracture mechanics concept was investigated with the
help of large scale specimens focusing on complex loading situations as th
ey result from postulated thermal shock events for the RPV. A series of pre
ssurized thermal shock (PTS) experiments were performed in which the applic
ability of the fracture mechanics parameters derived from small scale speci
men testing could be demonstrated. This includes brittle (static and dynami
c) crack initiation and crack arrest in the low Charpy energy regime as wel
l as stable crack initiation, stable crack growth and crack arrest in the u
pper shelf toughness regime. The paper provides the basic material data, th
e load paths, representative for lat ge complex components as well as exper
imental and theoretical results of PTS experiments. From these data it call
be concluded that the available fracture mechanics concepts can be used to
describe the component behavior under transient loading conditions. (C) 20
00 Elsevier Science S.A. All rights reserved.