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Droin J, Seiler N, Bertrand F, Manchon X, Sciora P. Safety-oriented SFR core design: Methodology and application to transient bifurcations and stability maps analyses. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109790] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/12/2023]
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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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Severe accident studies on the efficiency of mitigation devices in a SFR core with SIMMER code. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.111037] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Mitigation of severe accidents for SFR and associated event sequence assessment. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.110993] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Droin JB, Marie N, Bertrand F, Marrel A, Bachrata A. Design-oriented tool for Unprotected Loss Of Flow simulations in a Sodium Fast Reactor: Validation and application to stability analyses. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110550] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Bertrand F, Manchon X, Marie N, Droin J, Schmitt D, Lance M, Sciora P. Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110319] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Journeau C, Aufore L, Berge L, Brayer C, Cassiaut-Louis N, Estre N, Payot F, Piluso P, Prele JC, Singh S, Zabiégo M, Pluyette E, Serre F, Teisseire B. Corium-Sodium and Corium-Water Fuel-Coolant-Interaction Experimental Programs for the PLINIUS2 Prototypic Corium Platform. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1479580] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Affiliation(s)
| | - Laurence Aufore
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Léonie Berge
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Claude Brayer
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | | | - Nicolas Estre
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Frédéric Payot
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Pascal Piluso
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | | | - Shifali Singh
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Magali Zabiégo
- CEA, DEN, Cadarache, DTN, SMTA, 13108 Saint Paul lès Durance, France
| | - Eric Pluyette
- CEA, DEN, Cadarache, DTN, STCP, 13108 Saint Paul lès Durance, France
| | - Frédéric Serre
- CEA, DEN, Cadarache, DER, 13108 Saint Paul lès Durance, France
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Bertrand F, Marie N, Bachrata A, Brun-Magaud V, Droin J, Manchon X, Herbreteau K, Farges B, Carluec B, Poumerouly S, Lemasson D. Status of severe accident studies at the end of the conceptual design of ASTRID: Feedback on mitigation features. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.10.019] [Citation(s) in RCA: 22] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Manchon X, Bertrand F, Marie N, Lance M, Schmitt D. Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accident. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.07.010] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Droin JB, Marie N, Bachrata A, Bertrand F, Merle E, Seiler JM. Physical tool for Unprotected Loss Of Flow transient simulations in a Sodium Fast Reactor. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.03.035] [Citation(s) in RCA: 18] [Impact Index Per Article: 2.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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