Analysis of Integral Circulation and Decay Heat Removal Experiments in the Lead-Bismuth CIRCE Facility with RELAP5 Code
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G1-2 - Sodium Cooled Fast Reactors Design and Safety and Lead/Lead-Bismuth Cooled Reactors

Giacomino Bandini (ENEA)
Paride Meloni (ENEA)
Massimiliano Polidori (ENEA)
Pierantonio Gaggini (ENEA)
Mariano Tarantino (ENEA)
Andrea Ciampichetti (ENEA)


In this paper, the results of the post-test analysis of some integral circulation experiments conducted on the lead-bismuth CIRCE facility are presented in comparison with the experimental data. These experiments include the simulation of unprotected loss of flow and unprotected loss of heat sink transients in a pool-type heavy liquid metal reactor. Furthermore, the results of the pre-test analysis of a protected loss of heat sink and flow transient with decay heat removal by a heat exchanger immersed in the pool and operating in natural circulation is presented. All transient analyses have been performed with the RELAP5 thermal-hydraulic code.

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