Application of ASTEC V2.0 to Severe Accident Analyses for German Konvoi Type Reactors
NURETH-14 - 2011 September 25-30


Presented at:
NURETH-14
2011 September 25-30
Location:
Toronto, Canada
Session Title:
B4-1 Plant System Safety Code Development and Assessment

Authors:
Holger Nowack (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)
Walter Erdmann (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)
Nils Reinke (Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH)
  

Abstract

The integral code ASTEC [1] is jointly developed by IRSN (Institut de Radioprotection et deSûreté Nucléaire,France) and GRS (Germany). Its main objective is to simulate severe accident scenarios in PWRs from the initiating event up to the release of radioactive material into the environment. This paper describes the ASTEC modeling approach and the nodalisation of a KONVOI type PWR as an application example. Results from an integral severe accident study are presented and shortcomings as well as advantages are outlined. As a conclusion, the applicability of ASTEC V2.0 for deterministic severe accident analyses used for PSA level 2 and Severe Accident Management studies will be assessed.

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