NDLI: Application of the BEREMIN Model for Evidencing the Warm Pre-Stress Effect in an Irradiated Reactor Pressure Vessel Containing a Semi-Elliptical Subclad Defect Under Small and Large LOCA Conditions

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Gilles, Ph Izard, J. -P Devaux, J.
Copyright Year	2008
Abstract	The nuclear power plants lifetime is strongly dependent of the guarantee of the reactor pressure vessel (RPV) integrity. Therefore, the RPV integrity has to be demonstrated under the most severe configuration, namely the Pressurized Thermal Shock induced by the Loss of Coolant Accident induced by a large break in the primary loop. For such a transient, the apparent risk of failure is maximum when the load is decreasing; the fracture resistance decreasing rate being stronger. However, such type of loading generates an increase of the fracture resistance as shown by numerous studies (Chell, 1980 – BEREMIN, 1981 – Smith et al., 2004). This is known as the warm pre-stress (WPS) effect. This beneficial effect on the resistance to brittle fracture is not accounted for in the French RCCM and RSEM codes (RCCM, 2000 – RSEM, 2005). EDF has launched several R&D actions with CEA and AREVA as well as with European partners (SMILE, 2001) to validate and model the WPS effect under RPV representative conditions. Proving the existence of this beneficial load history effect (designated as Warm Pre Stress WPS), in the case of a defective RPV in emergency and faulted conditions is the aim of the present paper. The demonstration is conducted in the case of cleavage fracture using an improved version of the BEREMIN model. As opposite to the classical Fracture Mechanics methodology, this approach allows to account for load history effects on cleavage. The study analyzes the behavior of a semi-elliptical under clad crack in the EoL core shell of a 900 MWe RPV for two loading cases: the large break Loss Of Coolant Accident transient and a small break LOCA inducing thermal fluctuations on the vessel inner wall. The WPS effect is evidenced by comparing the plasticity corrected SIF levels of two loadings for the same value of failure probability: the considered WPS loading and a virtual monotonously increasing load applied at the temperature at which the brittle fracture risk is estimated.
Sponsorship	Pressure Vessels and Piping
Starting Page	421
Ending Page	427
Page Count	7
File Format	PDF
ISBN	9780791848265
DOI	10.1115/PVP2008-61809
e-ISBN	0791838285
Volume Number	Volume 3: Design and Analysis
Conference Proceedings	ASME 2008 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2008-07-27
Publisher Place	Chicago, Illinois, USA
Access Restriction	Subscribed
Subject Keyword	Local model Fracture mechanics Reactor pressure vessel Pressurized thermal shock Warm pre stress Reactor vessels Stress Thermal shock
Content Type	Text
Resource Type	Article

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