MELCOR is an integral code developed by Sandia National Laboratories (SNL) for the US Nuclear Regulatory Commission (USNRC) to perform severe accident analyses of Light Water Reactors (LWR). More recently, MELCOR capabilities are being extended also to analyze non-LWR fission technologies. Within the European MELCOR User Group (EMUG), organized in the framework of USNRC Cooperative Severe Accident Research Program (CSARP), an activity on the evaluation of the applicability of MELCOR 2.2 for fusion safety analyses has been launched and it has been coordinated by ENEA. The aim of the activity was to identify the physical models to be possibly implemented in MELCOR 2.2 necessary for fusion safety analyses, and to check if those models are already available in MELCOR 1.8.6 for fusion version, developed by Idaho National Laboratory (INL). From this activity, a list of modeling needs emerged from the safety analyses of fusion-related installations have been identified and described. Then, the importance of the various needs, intended as the priority for model implementation in the MELCOR 2.2 code, has been evaluated according to the technical expert judgement of the authors. In the present paper, the identified modeling needs are discussed. The ultimate goal would be to propose to have a single integrated MELCOR 2.2 code release capable to cover both fission and fusion applications.

Current status of MELCOR 2.2 for fusion safety analyses / Mascari, F.; Bersano, A.; Adorni, M.; D'Ovidio, G.; Martín-Fuertes, F.; Jin, X. Z.; Mazzini, G.; Gonfiotti, B.; Georgiev, G.; Leskovar, M.; Bertani, C.; Testoni, R.; Giannetti, F.; D'Onorio, M.; Agnello, G.; Di Maio, P. A.; Angelucci, M.; Paci, S.; Grippo, G.; Fernández-Cosials, K.; Dongiovanni, D.; Malicki, M.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - 194:(2023), pp. 1-7. [10.1016/j.fusengdes.2023.113869]

Current status of MELCOR 2.2 for fusion safety analyses

F. Giannetti
Membro del Collaboration Group
;
M. D'Onorio
Membro del Collaboration Group
;
2023

Abstract

MELCOR is an integral code developed by Sandia National Laboratories (SNL) for the US Nuclear Regulatory Commission (USNRC) to perform severe accident analyses of Light Water Reactors (LWR). More recently, MELCOR capabilities are being extended also to analyze non-LWR fission technologies. Within the European MELCOR User Group (EMUG), organized in the framework of USNRC Cooperative Severe Accident Research Program (CSARP), an activity on the evaluation of the applicability of MELCOR 2.2 for fusion safety analyses has been launched and it has been coordinated by ENEA. The aim of the activity was to identify the physical models to be possibly implemented in MELCOR 2.2 necessary for fusion safety analyses, and to check if those models are already available in MELCOR 1.8.6 for fusion version, developed by Idaho National Laboratory (INL). From this activity, a list of modeling needs emerged from the safety analyses of fusion-related installations have been identified and described. Then, the importance of the various needs, intended as the priority for model implementation in the MELCOR 2.2 code, has been evaluated according to the technical expert judgement of the authors. In the present paper, the identified modeling needs are discussed. The ultimate goal would be to propose to have a single integrated MELCOR 2.2 code release capable to cover both fission and fusion applications.
2023
advanced reactor safety; fusion reactor safety; MELCOR
01 Pubblicazione su rivista::01a Articolo in rivista
Current status of MELCOR 2.2 for fusion safety analyses / Mascari, F.; Bersano, A.; Adorni, M.; D'Ovidio, G.; Martín-Fuertes, F.; Jin, X. Z.; Mazzini, G.; Gonfiotti, B.; Georgiev, G.; Leskovar, M.; Bertani, C.; Testoni, R.; Giannetti, F.; D'Onorio, M.; Agnello, G.; Di Maio, P. A.; Angelucci, M.; Paci, S.; Grippo, G.; Fernández-Cosials, K.; Dongiovanni, D.; Malicki, M.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - 194:(2023), pp. 1-7. [10.1016/j.fusengdes.2023.113869]
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/1746603
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