PSA-Oriented Analysis of Transients in Atucha Unit II PHWR with a RELAP Model

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.