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Modak M, Nirgude VV, Park HS, Choi YJ, Seo MR. Experimental investigation of quenching phenomena in high temperature conical debris bed – Part 1: MONET tests. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112102] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/24/2022]
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Schiano T, Bigot B, Haquet JF, Saramito P, Smutek C. A viscoplastic approach to corium spreading during a severe nuclear accident. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112045] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/13/2022]
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Modak M, Nirgude VV, Park HS. Mapping of quench front propagation in a heated cylindrical particle bed – MONET tests. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112080] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Yokoyama R, Kondo M, Suzuki S, Johnson M, Miwa S, Pellegrini M, Denoix A, Bouyer V, Journeau C, Okamoto K. A Lagrangian approach to ex-vessel corium spreading over ceramic and concrete substrates using moving particle hydrodynamics. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112029] [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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Louie DL, Wang Y, Rao R, Kucala A, Kruichak J. Study of alkaline carbonate cooling to mitigate Ex-Vessel molten corium accidents. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111752] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Hotta A, Hadachi H, Kikuchi W, Shimizu M. Development of a horizontal two-dimensional melt spread analysis code, THERMOS-MSPREAD Part-2: Special models and validations based on dry spreading experiments using molten oxide mixtures and prototype corium. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111598] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Johnson M, Denoix A, Bouyer V, Goda H, Kamohara S, Takeuchi J, Brissonneau L, Journeau C. High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates. J NUCL SCI TECHNOL 2021. [DOI: 10.1080/00223131.2021.1977199] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Michael Johnson
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Arthur Denoix
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Viviane Bouyer
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Hiroshi Goda
- Reactor Core Safety Engineering Department, Nuclear Energy Systems Division, Mitsubishi Heavy Industries, Ltd., Kobe, Japan
| | - Satoru Kamohara
- Reactor Core Safety Engineering Department, Nuclear Energy Systems Division, Mitsubishi Heavy Industries, Ltd., Kobe, Japan
| | - Junichi Takeuchi
- Reactor Core Safety Engineering Department, Nuclear Energy Systems Division, Mitsubishi Heavy Industries, Ltd., Kobe, Japan
| | - Laurent Brissonneau
- CEA, DES, IRESNE, DTN, SMTA, LMCT, Cadarache, Saint-Paul-lez-Durance, France
| | - Christophe Journeau
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
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Johnson M, Schiano T, Denoix A, Bouyer V, Journeau C. High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface. J NUCL SCI TECHNOL 2021. [DOI: 10.1080/00223131.2021.1978895] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Michael Johnson
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Thomas Schiano
- CEA, DES, IRESNE, DTN, SMTA, LMAG, Saint-Paul-lez-Durance, France
| | - Arthur Denoix
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Viviane Bouyer
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
| | - Christophe Journeau
- CEA, DES, IRESNE, DTN, SMTA, LEAG, Cadarache, Saint-Paul-lez-Durance, France
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Dimensionless parameters controlling the spreading behaviors of free-falling molten metal on dry surface. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103882] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Inagaki K. Development of multiphysics particle method simulation code PHALSER and its application to various phenomena. J NUCL SCI TECHNOL 2021. [DOI: 10.1080/00223131.2021.1884138] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
Affiliation(s)
- Kenta Inagaki
- Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry, Kanagawa, Japan
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Podila K, Chen Q, Rao Y, Spencer J, Buell J, Morreale A, David R, Pfeiffer P. CFD simulation of corium flow through an end fitting of a pressurised heavy water reactor. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110850] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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12
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Jubaidah, Duan G, Yamaji A, Journeau C, Buffe L, Haquet JF. Investigation on corium spreading over ceramic and concrete substrates in VULCANO VE-U7 experiment with moving particle semi-implicit method. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107266] [Citation(s) in RCA: 12] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Sahboun N, Miwa S, Sawa K, Yamamoto Y, Watanabe Y, Ito T. A molten metal jet impingement on a flat spreading surface. J NUCL SCI TECHNOL 2020. [DOI: 10.1080/00223131.2020.1764406] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
Affiliation(s)
- Nassim Sahboun
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Shuichiro Miwa
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Kazuhiro Sawa
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Yasunori Yamamoto
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Yuta Watanabe
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
| | - Tomomasa Ito
- Division of Applied Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Sapporo, Japan
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Hotta A, Akiba M, Morita A, Konovalenko A, Villanueva W, Bechta S, Komlev A, Thakre S, Hoseyni SM, Sköld P, Matsumoto T, Sugiyama T, Buck M. Experimental and Analytical Investigation of Formation and Cooling Phenomena in High Temperature Debris Bed. J NUCL SCI TECHNOL 2019. [DOI: 10.1080/00223131.2019.1691078] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
- Akitoshi Hotta
- Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R), Tokyo, Japan
| | - Miyuki Akiba
- Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R), Tokyo, Japan
| | - Akinobu Morita
- Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority(S/NRA/R), Tokyo, Japan
| | - Alexander Konovalenko
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Walter Villanueva
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Sevostian Bechta
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Andrei Komlev
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Sachin Thakre
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Seyed Mohsen Hoseyni
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | - Per Sköld
- Division of Nuclear Power Safety, Department of Physics, School of Engineering Science, Royal Institute of Technology (KTH), Stockholm, Sweden
| | | | - Tomoyuki Sugiyama
- Japan Atomic Energy Agency, Nuclear Safety Research Center, Naka-gun, Japan
| | - Michael Buck
- Institute for Nuclear Technology and Energy Systems (IKE) University of Stuttgart, Stuttgart, Germany
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15
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On the numerical modelling of Corium spreading using Volume-of-Fluid methods. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.02.013] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Duan G, Yamaji A, Koshizuka S. A novel multiphase MPS algorithm for modeling crust formation by highly viscous fluid for simulating corium spreading. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.01.005] [Citation(s) in RCA: 39] [Impact Index Per Article: 7.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Ogura T, Matsumoto T, Miwa S, Hibiki T, Mori M. Experimental study on molten metal spreading and deposition behaviors on wet surface. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.03.001] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Yamashita S, Ina T, Idomura Y, Yoshida H. A numerical simulation method for molten material behavior in nuclear reactors. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.032] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Matsumoto T, Sakurada K, Miwa S, Sakashita H, Mori M. Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.04.038] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Investigation on influence of crust formation on VULCANO VE-U7 corium spreading with MPS method. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.04.002] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Preliminary feasibility study of post-flooding ex-vessel corium cooling strategy by CFD spreading simulations and concrete ablation analysis. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2016.12.017] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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YE INSOO, KIM JEONGEUNALICE, RYU CHANGKOOK, HA KWANGSOON, KIM HWANYEOL, SONG JINHO. NUMERICAL INVESTIGATION OF THE SPREADING AND HEAT TRANSFER CHARACTERISTICS OF EX-VESSEL CORE MELT. NUCLEAR ENGINEERING AND TECHNOLOGY 2013. [DOI: 10.5516/net.03.2012.011] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Kawahara T, Oka Y. Ex-vessel molten core solidification behavior by moving particle semi-implicit method. J NUCL SCI TECHNOL 2012. [DOI: 10.1080/00223131.2012.740944] [Citation(s) in RCA: 28] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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25
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CFD analysis of core melt spreading on the reactor cavity floor using ANSYS CFX code. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.08.047] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Arias F. Vapor explosions: Prediction of a critical liquid–corium velocity in vapor destabilization mechanism of corium melt in the fuel–coolant interactions – FCI. ANN NUCL ENERGY 2010. [DOI: 10.1016/j.anucene.2010.03.018] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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