The Reactor Pressure Vessel (RPV) is an essential component liable to limit
the life duration of PWR's. Its behavior in service is limited in time due
to the embrittling effects of irradiation. The structural integrity of the
RPV is assessed by conventional fracture mechanical studies, where it is a
ssumed that the failure of a flawed structure occurs when the stress intens
ity factor at the crack tip reaches the toughness value of the structure ma
terial. Toughness curves of materials are obtained from monotonously increa
sing and isothermal loading. On the other hand, RPV integrity assessment in
volves loading conditions with coupled cooling, heating, increasing and dec
reasing load.
The safety analyses made at the European level study, the behavior of defec
ts in the vessel subjected to loading resulting from thermal transients. Th
ese analyses usually do not take into account the effect of load history/wa
rm pre-stressing (WPS) of the defects, which is observed in a wide range of
experimental studies. The non-consideration of the beneficial effect of th
is physical phenomenon has two major consequences:
. a poor knowledge of the real margins associated with the transients to wh
ich the vessel is subjected,
. an economical penalty due to large under-estimation of the life duration
of the vessel.
This paper presents the results of two independent programs.
The first dealing with four WPS tests performed at CEA in France on CT spec
imens manufactured of ferritic 18MND5 steel undergoing different types of l
oading during the cooling phase as follow:
. Load Cool Fracture (LCF)
. Loading Maintained CMOD Cooling Fracture (LM2CF)
WPS effect is observed in the first case, while curve in the second case th
e failure occurs during the crossing of the transition because of the monot
onous increase of the force due to constant CMOD (Crack Mouth Opening Displ
acement).
The second program deals with tests performed at MPA in Germany in collabor
ation with EDF on CT25 and CT50 specimens using the same material with five
types of WPS cycles:
. LCF
. Load Unload Cool Fracture (LUCF)
. Load Transient Fracture (LTF)
. Load Oscillation Cool Fracture (LOCF)
. Load Oscillation Transient Fracture (LOTF)
In all these cases, WPS effect is demonstrated.
For both the programs, numerical analyses were performed at MPA using Weibu
ll [Metall Trans A, 14A (1987) 2277] and Chell [Fourth Int Conf Pressure Ve
ssel Technol, Inst Mech Engng, 1980, Paper C22/80, London, U.K., 117] model
s to predict the WPS effect, details of which are presented here. (C) 2001
Published by Elsevier Science Ltd.