Several innovative solutions for a liquid metal fast reactor design are being investigated within the framework of the ELSY (the acronym for the European Lead-cooled System) Sixth Framework Programme of URATOM. Among these solutions the open-assembly core option adopted by ENEA for the preliminary neutronic analysis requires a new approach to the thermal-hydraulic core design. In addition, it could have important implication on the reactor safety. Therefore a two-step approach at the T/H analysis of the core is being followed: Utilization of a one-dimensional RELAP5 model for independent channels analysis for a prompt verification of the thermal-hydraulic and safety of the core neutronic design. Development of a dedicated tool for the evaluation of the intermingled effects between assembly flows.

A Two-step Approach for the Preliminary Evaluation of the Thermal-hydraulics and Safety of the ELSY Open Square Core Design

MANSERVISI, SANDRO;
2009

Abstract

Several innovative solutions for a liquid metal fast reactor design are being investigated within the framework of the ELSY (the acronym for the European Lead-cooled System) Sixth Framework Programme of URATOM. Among these solutions the open-assembly core option adopted by ENEA for the preliminary neutronic analysis requires a new approach to the thermal-hydraulic core design. In addition, it could have important implication on the reactor safety. Therefore a two-step approach at the T/H analysis of the core is being followed: Utilization of a one-dimensional RELAP5 model for independent channels analysis for a prompt verification of the thermal-hydraulic and safety of the core neutronic design. Development of a dedicated tool for the evaluation of the intermingled effects between assembly flows.
Proceeding of 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
1
12
P. Meloni; G. Bandini; A. Cervone; S. Manservisi; M. Polidori
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/79195
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