Published 2006 | Version v1
Book

Insights from a Full Scope Level 2 PSA Model for a PWR Plant With Spherical Shell Containment

  • 1. Kernkraftwerk Gosgen Daniken AG, CH-4658 Daeniken (Switzerland)
  • 2. Southern California Edison (United States)
  • 3. ABSG Consulting, Inc. (United States)

Description

A full scope Level 2 PSA was performed in 2005 for a three-loop PWR plant with spherical shell containment. New regulatory definition of large early release, and new reporting requirement related to large late release drive the technical approach in this study. New plant features, new accident management guidelines, and new thermal hydraulics and source terms calculations were incorporated in the linked Level 1 and Level 2 model. The plant features observed to be important for accident mitigation include: 1) primary depressurization; 2) accident induced hot leg failure; 3) hydrogen burn mitigation; and 4) containment filtered venting. (authors)

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers - ASME
Imprint Place
New York (United States)
Imprint Pagination
8 p.

Conference

Title
14. international conference on nuclear engineering (ICONE 14)
Dates
17-20 Jul 2006
Place
Miami, FL (United States)