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Bertrand F, Bachrata A, Seiler N, Droin J, Mouly A. Studies and cross-comparisons of severe accident prevention and mitigation capabilities of a SFR and a GFR. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111838] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Bachrata A, Bertrand F, Marie N, Serre F. A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2021. [DOI: 10.1115/1.4047921] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
The nuclear safety approach has to cover accident sequences involving core degradation in order to develop reliable mitigation strategies for both existing and future reactors. In particular, the long-term stabilization of the degraded core materials and their coolability has to be ensured after a severe accident. This paper focuses on severe accident phenomena in pressurized water reactors (PWR) compared to those potentially occurring in future GenIV-type sodium fast reactors (SFR). First, the two considered reactor concepts are introduced by focusing on safety aspects. The severe accident scenarios leading to core melting are presented and the initiating events are highlighted. This paper focuses on in-vessel severe accident phenomena, including the chronology of core damage, major changes in the core configuration and molten core progression. Regarding the mitigation means, the in-vessel retention phenomena and the core catcher characteristics are reviewed for these different nuclear generation concepts (II, III, and IV). A comparison between the PWR and SFR severe accident evolution is provided as well as the relation between governing physical parameters and the adopted mitigation provisions for each reactor concept. Finally, it is highlighted how the robustness of the safety demonstration is established by means of a combined probabilistic and deterministic approach.
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Affiliation(s)
- Andrea Bachrata
- Commissariat à l'énergie atomique et aux énergies alternatives (CEA), IRESNE, DER, Saint Paul lez Durance F-13108, France
| | - Fréderic Bertrand
- Commissariat à l'énergie atomique et aux énergies alternatives (CEA), IRESNE, DER, Saint Paul lez Durance F-13108, France
| | - Nathalie Marie
- Commissariat à l'énergie atomique et aux énergies alternatives (CEA), IRESNE, DER, Saint Paul lez Durance F-13108, France
| | - Fréderic Serre
- Commissariat à l'énergie atomique et aux énergies alternatives (CEA), IRESNE, DER, Saint Paul lez Durance F-13108, France
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Bertrand F, Marie N, Bachrata A, Droin J, Manchon X, Le Meute T, Merle E, Heuer D. Simplified criteria for a comparison of the accidental behaviour of Gen IV nuclear reactors and of PWRS. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.110962] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Farkas I, Farkas T, Nagy AG, Mayer G. Determination of pressure loss coefficient of the hot duct break of the CEA ALLEGRO 2009 concept using a CFD technique. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.05.016] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Marie N, Marrel A, Seiler J, Bertrand F. Physico-statistical approach to assess the core damage variability due to a total instantaneous blockage of SFR fuel sub-assembly. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2015.07.012] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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The effect of the different parameters on the infinite multiplication factor of Gas-Cooled Fast Reactors. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.10.019] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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György H, Czifrus S. Burnup calculation of the Generation IV reactors. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.01.015] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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