The considered research activity deals with the application of a chain of numerical codes, in order to develop a computational tool for Pressurized Thermal Shock (PTS) analysis. Nuclear reactor pressure vessel structural integrity is concerned regarding the risk of brittle fracture. Special reference is made to the identification of the 3D Stress-Strain State of the WWER-1000 pressure vessel. A Main Steam Line Break (MSLB) accident has been taken as reference scenario for the study. The thermal hydraulic calculation has been carried out using Relap5/mod3.3 code. The results are used for computing the combined effect of thermal and pressure loading, which constitutes the initial event for the PTS. Those data supply the input for the structural mechanics code. The Stress-Strain State of the WWER-1000 reactor pressure vessel has been evaluated by means of the Ansys 5.7 code.
Fracture Mechanics Analysis of Generic WWER-1000 RPV in PTS Event
BEGHINI, MARCO;D'AURIA, FRANCESCO SAVERIO
2003-01-01
Abstract
The considered research activity deals with the application of a chain of numerical codes, in order to develop a computational tool for Pressurized Thermal Shock (PTS) analysis. Nuclear reactor pressure vessel structural integrity is concerned regarding the risk of brittle fracture. Special reference is made to the identification of the 3D Stress-Strain State of the WWER-1000 pressure vessel. A Main Steam Line Break (MSLB) accident has been taken as reference scenario for the study. The thermal hydraulic calculation has been carried out using Relap5/mod3.3 code. The results are used for computing the combined effect of thermal and pressure loading, which constitutes the initial event for the PTS. Those data supply the input for the structural mechanics code. The Stress-Strain State of the WWER-1000 reactor pressure vessel has been evaluated by means of the Ansys 5.7 code.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
