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Zhao L, Punetha M, Ma W, Konovalenko A, Bechta S. Simulation of melt spreading over dry substrates with the moving particle Semi-implicit method. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112229] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 03/03/2023]
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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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3
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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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Li X, Yamaji A, Duan G, Sato I, Furuya M, Madokoro H, Ohishi Y. Estimation of debris relocation and structure interaction in the pedestal of Fukushima Daiichi Nuclear Power Plant Unit-3 with Moving Particle Semi-implicit (MPS) method. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108923] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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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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Journeau C, Bouyer V, Charollais F, Chikhi N, Delacroix J, Denoix A, Laffolley H, Mattassoglio C, Molina D, Piluso P, Sauvecane P, Thilliez S, Turquais B, Suteau C. Upgrading the PLINIUS platform toward smarter prototypic-corium experimental R&D. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111511] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Sato I. Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111426] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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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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11
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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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12
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Jubaidah, Umazume Y, Takahashi N, Li X, Duan G, Yamaji A. 2D MPS method analysis of ECOKATS-V1 spreading with crust fracture model. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111251] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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13
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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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Na H, Kang DG, Ryu YH, Lee HJ. One-dimensional ex-vessel coolability analysis of debris beds formed in OPR1000 pre-flooded reactor cavity. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107123] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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16
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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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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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19
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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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Zhang YP, Niu SP, Zhang LT, Qiu SZ, Su GH, Tian WX. A Review on Analysis of LWR Severe Accident. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2015. [DOI: 10.1115/1.4030364] [Citation(s) in RCA: 37] [Impact Index Per Article: 4.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
A severe accident (SA) is defined as an incident involving melting of the nuclear reactor core and the release of fission products (FP) from the fuel and their associated risks. In the SA, the containment may fail, causing the public hazard of fission products released to the environment. This review elaborates the resolved issues of SAs under the condition of a hypothetical SA. SA research that has been performed over the years is briefly described, including various SA scenarios. The SA scenarios involve core melt scenarios from the beginning of core degradation to melt formation and relocation into the lower head and to the containment, the interactions of the molten corium with water and concrete, the behavior of fission products in- and ex-vessel, hydrogen-related phenomena, and all associated risks. The mitigation strategies that have been adopted in existing reactors and advanced light water reactors (ALWR) are also discussed. These mitigation measures can keep the reactor vessel or containment intact and terminate the SA progression. SA analysis codes are then summarized and divided into three categories, namely, systematic analysis codes, mechanism analysis codes, and single-function analysis codes. Next, the unresolved issues of SAs are proposed, including narrow gap cooling, melt chemical interactions, steam explosion loads, molten debris coolability, and iodine chemistry. Further experimental and theoretical research activities should be conducted to resolve these issues; consequently, some recommendations for further research work are also given in the last part of this review. This review aims to add to the knowledge and understanding of SA research in the past few decades and to benefit further research of SAs.
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Affiliation(s)
- Y. P. Zhang
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
| | - S. P. Niu
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
| | - L. T. Zhang
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
| | - S. Z. Qiu
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
| | - G. H. Su
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China e-mail:
| | - W. X. Tian
- Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
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Youn YS, Kim JG, Park SD, Ha YK. Temperature-dependent Variations of the Interface between UO 2and Zr. B KOREAN CHEM SOC 2015. [DOI: 10.1002/bkcs.10403] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Young-Sang Youn
- Nuclear Chemistry Research Division; Korea Atomic Energy Research Institute; Yuseong-gu, Daejeon 34057 Republic of Korea
| | - Jong-Goo Kim
- Nuclear Chemistry Research Division; Korea Atomic Energy Research Institute; Yuseong-gu, Daejeon 34057 Republic of Korea
| | - Soon Dal Park
- Nuclear Chemistry Research Division; Korea Atomic Energy Research Institute; Yuseong-gu, Daejeon 34057 Republic of Korea
| | - Yeong-Keong Ha
- Nuclear Chemistry Research Division; Korea Atomic Energy Research Institute; Yuseong-gu, Daejeon 34057 Republic of Korea
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Krotov V, Filatov Y. Anomalous Influence of Electrochemically Inert ZrCl4 on UO2 Current Efficiency During Electrolysis in (NaCl-KCl)equim-UO2Cl2-ZrCl4 Melt. Electrochim Acta 2014. [DOI: 10.1016/j.electacta.2014.08.013] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Krotov V, Filatov Y. Regularities of cathode deposit formation during simultaneous reduction and exchange reactions. Influence of the electrolysis conditions on the concentration of components in the UO2-ZrO2 cathode deposit. Electrochim Acta 2014. [DOI: 10.1016/j.electacta.2013.11.071] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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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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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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Christophe J, Piluso P, Correggio P, Ferry L, Fritz G, Haquet JF, Monerris J, Ruggieri JM, Sanchez-Brusset M, Parga C. CONTRIBUTIONS OF THE VULCANO EXPERIMENTAL PROGRAMME TO THE UNDERSTANDING OF MCCI PHENOMENA. NUCLEAR ENGINEERING AND TECHNOLOGY 2012. [DOI: 10.5516/net.03.2012.703] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Journeau C, Piluso P, Haquet JF, Boccaccio E, Saldo V, Bonnet JM, Malaval S, Carénini L, Brissonneau L. Two-dimensional interaction of oxidic corium with concretes: The VULCANO VB test series. ANN NUCL ENERGY 2009. [DOI: 10.1016/j.anucene.2009.07.006] [Citation(s) in RCA: 35] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Large-scale ECOKATS experiments: Spreading of oxide melt on ceramic and concrete surfaces. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2006.03.010] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Journeau C, Haquet JF, Spindler B, Spengler C, Foit J. The VULCANO VE-U7 Corium spreading benchmark. PROGRESS IN NUCLEAR ENERGY 2006. [DOI: 10.1016/j.pnucene.2005.09.009] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Spindler B, Veteau J. The simulation of melt spreading with THEMA code. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2005.09.016] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Spindler B, Veteau J. The simulation of melt spreading with THEMA code. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2005.09.009] [Citation(s) in RCA: 15] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Spreading under variable viscosity and time-dependent boundary conditions: estimate of viscosity from spreading experiments. NUCLEAR ENGINEERING AND DESIGN 2004. [DOI: 10.1016/j.nucengdes.2003.10.002] [Citation(s) in RCA: 14] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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