Reactor Pressure Vessel integrity is one of the main concerns related to license renewals and plant-life extension. A research activity is conducted at the “Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione” - University of Pisa to develop computational tools able to predict the brittle propagation of flaw in VVER-1000 Reactor Pressure Vessel. IAEA-EBP-VVER-08, Guidelines on Pressurised Thermal Shock Analysis for WWER Power Plant has been taken as a reference to address specific requirements for Thermal-Hydraulic, Structural and Fracture Mechanics analyses needed to be performed in case of Pressurised Thermal Shock event. Deterministic investigation is conducted by coupling complex codes suitable for deep insight in each different technical aspect involved in the Pressurised Thermal Shock analysis. The evaluation of thermal and mechanical loads acting on the pressure wall and of the nominal stresses induced in the undamaged structure, and the assessment of the Stress Intensity Factor for postulated cracks are described

PTS analysis methodology for VVER-1000 RPV by coupled codes

BEGHINI, MARCO;D'AURIA, FRANCESCO SAVERIO;
2004

Abstract

Reactor Pressure Vessel integrity is one of the main concerns related to license renewals and plant-life extension. A research activity is conducted at the “Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione” - University of Pisa to develop computational tools able to predict the brittle propagation of flaw in VVER-1000 Reactor Pressure Vessel. IAEA-EBP-VVER-08, Guidelines on Pressurised Thermal Shock Analysis for WWER Power Plant has been taken as a reference to address specific requirements for Thermal-Hydraulic, Structural and Fracture Mechanics analyses needed to be performed in case of Pressurised Thermal Shock event. Deterministic investigation is conducted by coupling complex codes suitable for deep insight in each different technical aspect involved in the Pressurised Thermal Shock analysis. The evaluation of thermal and mechanical loads acting on the pressure wall and of the nominal stresses induced in the undamaged structure, and the assessment of the Stress Intensity Factor for postulated cracks are described
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/202673
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