PSA-Oriented Analysis of Transients in Atucha Unit II PHWR with a RELAP Model
International Conference on the Future of Heavy Water Reactors - 2011 October 02-05


Presented at:
International Conference on the Future of Heavy Water Reactors
2011 October 02-05
Location:
Ottawa, Canada
Session Title:
Safety Analyses

Authors:
J. González (Comisión Nacional de Energía Atómica)
P. Zanocco (Comisión Nacional de Energía Atómica)
M. Giménez (Comisión Nacional de Energía Atómica)
M. Schivo (Nucleoeléctrica Argentina S.A.)
O. Mazzantini (Nucleoeléctrica Argentina S.A.)
M. Caputo (Comisión Nacional de Energía Atómica)
G. Bedrossian (Comisión Nacional de Energía Atómica)
P. Serrano (Nucleoeléctrica Argentina S.A.)
A. Vertullo (Comisión Nacional de Energía Atómica)
  

Abstract

This paper presents a model of the Atucha II (PHWR) nuclear power plant developed for RELAP5/MOD3.3. The nodalization was implemented to comply with the Probabilistic Safety Analysis required in the licensing, commissioning, and operating process. A data management platform is implemented that processes the geometric and physical data for nodalization and generates the code input. The steady state is analyzed by comparing calculated variables with their respective design values and previous calculations performed with other models/tools. Finally, a case of loss of heat sink caused by an electrical supply failure is analyzed.

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