The TRADE experiment is conceived to demonstrate the feasibility of the ADS concept at a power representative size. It is based on coupling of TRIGA reactor (ENEA-Casaccia) in subcritical core configuration with a proton accelerator (cyclotron) by means of a neutron spallation target interface and it is aimed at demonstrating the feasibility of the ADS concept at a power representative size. The RELAPS/PARCS code is considered a suitable tool for studying the coupled neutronics/thermal-hydraulics problem due to the capability of RELAP5 to treat Iight water reactors and of PARCS version modified by ENEA to simulate the three-dimensional neutronics of subcritical systems. Starting from a satisfactory assessment of the PARCS modifications against a simple analytical solution o! subcritical neutronics of TRADE (kinetics pseudo-potentials method), this paper presents the development of a quite detailed model for the coupled code able to evaluate the thermal feedback effects and to simulate the control rod action. The calculated transients represent a wide range of both operational and incidental scenarios in order to obtain a first system response lo a number of reactor elementary events at different subcritical levels. The results of the analysis show that the model could be a useful tool for the definition o! the operational procedures and incidental analysis, highlighting inherent safety behavior of the TRIGA reactor.

A Neutronics-Thermalhydraulics Model for Preliminary Studies on Trade Dynamics

Meloni, P.
2006-02-24

Abstract

The TRADE experiment is conceived to demonstrate the feasibility of the ADS concept at a power representative size. It is based on coupling of TRIGA reactor (ENEA-Casaccia) in subcritical core configuration with a proton accelerator (cyclotron) by means of a neutron spallation target interface and it is aimed at demonstrating the feasibility of the ADS concept at a power representative size. The RELAPS/PARCS code is considered a suitable tool for studying the coupled neutronics/thermal-hydraulics problem due to the capability of RELAP5 to treat Iight water reactors and of PARCS version modified by ENEA to simulate the three-dimensional neutronics of subcritical systems. Starting from a satisfactory assessment of the PARCS modifications against a simple analytical solution o! subcritical neutronics of TRADE (kinetics pseudo-potentials method), this paper presents the development of a quite detailed model for the coupled code able to evaluate the thermal feedback effects and to simulate the control rod action. The calculated transients represent a wide range of both operational and incidental scenarios in order to obtain a first system response lo a number of reactor elementary events at different subcritical levels. The results of the analysis show that the model could be a useful tool for the definition o! the operational procedures and incidental analysis, highlighting inherent safety behavior of the TRIGA reactor.
Relazione di convegno o conferenzaReattori sottocritici/ADS;Fisica dei reattori nucleari;Neutronica;Fluidodinamica
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5201
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