Analysis of protected accidental transients in the EFIT reactor with the RELAP5 thermal-hydraulic code

Francesco Castiglia, Mariarosa Giardina, Massimiliano Polidori, Paride Meloni, Giacomino Bandini, Maddalena Casamirra

Risultato della ricerca: Otherpeer review

1 Citazioni (Scopus)

Abstract

The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility of transmutation process through the Accelerator Driven System (ADS) route on an industrial scale. The conceptual design of this reactor of about 400 MW thermal power is under development in the frame of theEuropean EUROTPANS Integrated Project of the EURATOM Sixth Framework Program (FP6).EFIT is a pool-type reactor cooled by forced circulation of lead in the primary system where the heat is removed by steam generators installed inside thereactor vessel. The reactor power is sustained by a spallation neutron source supplied by a proton beam impinging on a lead target at the core centre. A safety-related Decay Heat Removal (DHR) system provided with four independent inherently safe loops is installed in the primary vessel to remove the decay heat in case of loss of secondary circuits heat removal capability. A quite detailed model of the EFIT reactor has been developed for the RELAP5 thermal-hydraulic code to be used in preliminary accidental transient analyses aimed at verifying the validity of the adopted solutions for the current reactor design with respect to the safety requirements, and confirm the inherent safety behavior of the reactor, such as decay heat removal in accidental conditions relying on natural circulation in the primary system.The accident analyses for the EFIT reactor include both protected and unprotected transients, on whether the reactor automatic trip, consisting in proton beam switch off, is actuated or not by the protection system. In this paper, the main results of the analyses of some protected transients with RELAP5 are presented. The analyzed transients concern the Protected Loss of Heat Sink (PLOHS), in which the DHR system plays a key role in bringing the reactor insafe conditions, and the Protected Loss of Flow (PLOF) transients with partial or total loss of forced circulation in the primary system.
Lingua originaleEnglish
Pagine759-768
Numero di pagine9
Stato di pubblicazionePublished - 2008

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