A spent fuel pool is a temporary storage facility designed to store the nuclear fuel assemblies removed from the reactor core. Here, the depleted fuel is vertically arranged in racks structures, accurately spaced to ensure subcriticality safety margins. Until the events occurred at the Fukushima Daiichi power plants, severe accidents in spent fuel pools had never been considered as a major safety concern, mainly because of their slow progression. However, extremely unlikely accident events, aggravated by the loss of site power, highlighted the vulnerability of nuclear fuel stored within spent fuel pools. During these accident sequences, reactor fuel rods can generate enough decay heat to vaporize the coolant around them, causing, during unmitigated scenarios, the uncovering and melting of fuel bundles after several days. In past years, new features have been introduced in the MELCOR code for the evaluation of potential risks associated to accident progression in spent fuel pools. In this paper, the accidental sequence of a loss of cooling accident in a boiling water reactor spent fuel pool is analysed with version 2.2 of the MELCOR code. The spent fuel pool of the Fukushima Daiichi unit 4 has been selected as reference. Main accident events, such as fuel uncovering, claddings oxidation, hydrogen generation, and fission products release, have been analysed assuming the unavailability of safety systems.

Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR / D'Onorio, M.; Maggiacomo, A.; Giannetti, F.; Caruso, G.. - In: JOURNAL OF PHYSICS. CONFERENCE SERIES. - ISSN 1742-6588. - 2177:1(2022), pp. 1-9. ((Intervento presentato al convegno 38th UIT Heat transfer international conference 2021, UIT 2021 tenutosi a Gaeta; Italy (online) [10.1088/1742-6596/2177/1/012020].

Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR

D'Onorio M.
Primo
;
Giannetti F.
Penultimo
;
Caruso G.
Ultimo
2022

Abstract

A spent fuel pool is a temporary storage facility designed to store the nuclear fuel assemblies removed from the reactor core. Here, the depleted fuel is vertically arranged in racks structures, accurately spaced to ensure subcriticality safety margins. Until the events occurred at the Fukushima Daiichi power plants, severe accidents in spent fuel pools had never been considered as a major safety concern, mainly because of their slow progression. However, extremely unlikely accident events, aggravated by the loss of site power, highlighted the vulnerability of nuclear fuel stored within spent fuel pools. During these accident sequences, reactor fuel rods can generate enough decay heat to vaporize the coolant around them, causing, during unmitigated scenarios, the uncovering and melting of fuel bundles after several days. In past years, new features have been introduced in the MELCOR code for the evaluation of potential risks associated to accident progression in spent fuel pools. In this paper, the accidental sequence of a loss of cooling accident in a boiling water reactor spent fuel pool is analysed with version 2.2 of the MELCOR code. The spent fuel pool of the Fukushima Daiichi unit 4 has been selected as reference. Main accident events, such as fuel uncovering, claddings oxidation, hydrogen generation, and fission products release, have been analysed assuming the unavailability of safety systems.
38th UIT Heat transfer international conference 2021, UIT 2021
boiling water reactors; fuel storage; hydrogen production;
04 Pubblicazione in atti di convegno::04c Atto di convegno in rivista
Analysis of Fukushima Daiichi unit 4 spent fuel pool using MELCOR / D'Onorio, M.; Maggiacomo, A.; Giannetti, F.; Caruso, G.. - In: JOURNAL OF PHYSICS. CONFERENCE SERIES. - ISSN 1742-6588. - 2177:1(2022), pp. 1-9. ((Intervento presentato al convegno 38th UIT Heat transfer international conference 2021, UIT 2021 tenutosi a Gaeta; Italy (online) [10.1088/1742-6596/2177/1/012020].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/1647439
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