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Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2

Author

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  • Alain Flores y Flores

    (National Radiation Protection Institute (SURO v.v.i.), Bartoškova 28, 140 00 Praha, Czech Republic
    Centre Řež, CV Řež, s. r. o., Hlavní 130, Řež, 250 68 Husinec, Czech Republic)

  • Danilo Ferretto

    (National Radiation Protection Institute (SURO v.v.i.), Bartoškova 28, 140 00 Praha, Czech Republic)

  • Tereza Marková

    (Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, V Holešovičkách 2, 180 00 Praha, Czech Republic)

  • Guido Mazzini

    (National Radiation Protection Institute (SURO v.v.i.), Bartoškova 28, 140 00 Praha, Czech Republic
    Centre Řež, CV Řež, s. r. o., Hlavní 130, Řež, 250 68 Husinec, Czech Republic)

Abstract

The severe accident integral codes such as Methods for Estimation of Leakages and Consequences of Releases (MELCOR) are complex tools used to simulate and analyse the progression of a severe accident from the onset of the accident up to the release from the containment. For this reason, these tools are developed in order to simulate different phenomena coupling models which can simulate simultaneously the ThermoHydraulic (TH), the physics and the chemistry. In order to evaluate the performance in the prediction of those complicated phenomena, several experimental facilities were built in Europe and all around the world. One of these facilities is the PHEBUS built by Institut de Radioprotection et de Sûrete Nucléaire (IRSN) in Cadarache. The facility reproduces the severe accident phenomena for a pressurized water reactor (PWR) on a volumetric scale of 1:5000. This paper aims to continue the assessment of the MELCOR code from version 2.1 up to version 2.2 underlying the difference in the fission product transport. The assessment of severe accident is an important step to the sustainability of the nuclear energy production in this period where the old nuclear power plants are more than the new reactors. The analyses presented in this paper focuses on models assessment with attention on the influence of B 4 C oxidation on the release and transport of fission products. Such phenomenon is a concern point in the nuclear industry, as was highlighted during the Fukushima Daiichi accident. Simulation of the source term is a key point to evaluate the severe accident hazard along with other safety aspects.

Suggested Citation

  • Alain Flores y Flores & Danilo Ferretto & Tereza Marková & Guido Mazzini, 2021. "Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2," Sustainability, MDPI, vol. 13(14), pages 1-32, July.
    • Handle: RePEc:gam:jsusta:v:13:y:2021:i:14:p:7964-:d:595645
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    References listed on IDEAS

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    1. Okubo, Toshihiro & Narita, Daiju & Rehdanz, Katrin & Schröder, Carsten, 2020. "Preferences for Nuclear Power in Post-Fukushima Japan: Evidence from a Large Nationwide Household Survey," EconStor Open Access Articles and Book Chapters, ZBW - Leibniz Information Centre for Economics, vol. 13(11).
    2. Seoyong Kim & Sunhee Kim, 2017. "Impact of the Fukushima Nuclear Accident on Belief in Rumors: The Role of Risk Perception and Communication," Sustainability, MDPI, vol. 9(12), pages 1-21, November.
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