Comparative analysis of pressure vessel integrity for various LOCA conditions


Colak U. , OZDERE O.

JOURNAL OF NUCLEAR MATERIALS, vol.297, no.3, pp.271-278, 2001 (Journal Indexed in SCI) identifier identifier

  • Publication Type: Article / Article
  • Volume: 297 Issue: 3
  • Publication Date: 2001
  • Doi Number: 10.1016/s0022-3115(01)00641-9
  • Title of Journal : JOURNAL OF NUCLEAR MATERIALS
  • Page Numbers: pp.271-278

Abstract

In this study, integrity analysis is performed for a classical four loop PWR pressure vessel fabricated from SA533B type ferritic steel. Pressure vessel behavior is analyzed by deterministic and probabilistic methods under transient conditions, which may cause pressurized thermal shock (PTS). In deterministic analysis, the change of material properties and the mechanical state of the vessel are analyzed against changes in coolant pressure and temperature. Probabilistic analysis is performed to obtain pressure vessel beltline region weld failure probabilities in transient conditions. Overall vessel failure probabilities are evaluated based on the results of deterministic analyses. Computer code VISA-II is utilized for the calculation of vessel failure probabilities. Among three cases considered in this study, a medium break loss of coolant accident induced by a 50 cm(2) break in the hot leg yields the highest vessel rupture probability. The maximum nil ductility temperature in all cases is still below the NRC PTS limit. (C) 2001 Elsevier Science B.V. All rights reserved.