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Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2

Nuclear technology, 2020-10, Vol.206 (10), p.1517-1537

2020

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Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project

Nuclear engineering and design, 2020-12, Vol.369, p.110857, Article 110857

2020

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Analysis of muon radiography of the Toshiba nuclear critical assembly reactor

Applied physics letters, 2014-01, Vol.104 (2)

2014

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Development of the source term PIRT based on findings during Fukushima Daiichi NPPs accident

Nuclear engineering and design, 2015-05, Vol.286, p.163-174

2015

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Update of the First TEPCO MAAP Accident Analysis of Units 1, 2, and 3 at Fukushima Daiichi Nuclear Power Station

Nuclear technology, 2014-05, Vol.186 (2), p.263-279

2014

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Investigation of the status of Unit 2 nuclear reactor of the Fukushima Daiichi by Cosmic Muon Radiography

Progress of theoretical and experimental physics, 2021-02, Vol.2021 (2)

2021

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Study of the Unit-3 nuclear reactor of Fukushima Daiichi by cosmic muon radiography

Progress of theoretical and experimental physics, 2022-01, Vol.2022 (1)

2022

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Progress status and future issues of development of analysis and estimation technology for fuel debris characterization (2): Mid-and-Long term plan for accident investigation and progress status of samples obtained at the Fukushima Daiichi NPS

Journal of the Atomic Energy Society of Japan, 2024, Vol.66 (2), p.70-73

2024

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MAAP code analysis focusing on the fuel debris condition in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 2

Nuclear engineering and design, 2023-04, Vol.404, p.112205, Article 112205

2023

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Transient behaviour and heat transfer characteristics in debris beds: Simulation and analysis of the LIVEJ2 experiment

Annals of nuclear energy, 2025-01, Vol.210, p.110854, Article 110854

2025

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Validation and application of numerical modeling for in-vessel melt retention in corium pools

International journal of heat and mass transfer, 2022-11, Vol.196, p.123313, Article 123313

2022

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MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3

Nuclear engineering and design, 2024-06, Vol.422, p.113088, Article 113088

2024

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MAAP code analysis focusing on the fuel debris conditions in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 3

Nuclear engineering and design, 2023-12, Vol.414, p.112574, Article 112574

2023

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Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3

Nuclear technology, 2023-06, Vol.209 (6), p.902-927

2023

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Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2

Journal of nuclear science and technology, 2024-11, Vol.61 (11), p.1453-1469

2024

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The Experimental and Simulation Results of LIVE-J2 Test-Investigation on Heat Transfer in a Solid-Liquid Mixture Pool

Nuclear technology, 2023-02, Vol.209 (2), p.144-168

2023

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Inference of containment depressurization scenario of Fukushima Daiichi Nuclear Power Plant Unit-2 during the Morning of March 15th, 2011

Journal of nuclear science and technology, 2021-04, Vol.58 (4), p.426-433

2021

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Unsolved issues related to thermal-hydraulics in the suppression chamber during Fukushima Daiichi accident progressions

Journal of nuclear science and technology, 2016-05, Vol.53 (5), p.630-638

2016

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INTERACTION BETWEEN BWR FUEL CLADDING AND FUEL COMPONENTS IN EARLY PHASE OF SEVERE ACCIDENT

Proceedings of the International Topical Workshop on Fukushima Decommissioning Research, 2022, Vol.2022, p.1048

2022

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ESTIMATION OF THE RELATIONSHIP BETWEEN THE PCV->R/B GAS-LEAK MECHANISM AND THE HYDROGEN EXPLOSION IN 1F3

Proceedings of the International Topical Workshop on Fukushima Decommissioning Research, 2022, Vol.2022, p.1053

2022

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RECENT FINDINGS FROM FUKUSHIMA DAIICHI UNIT 1 PRIMARY CONTAINMENT VESSEL INVESTIGATIONS

Proceedings of the International Topical Workshop on Fukushima Decommissioning Research, 2022, Vol.2022, p.1060

2022

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EVALUATION OF TEMPERATURE AND HYDROGEN/WATER VAPOR RATIO IN 1F2 CORE ON MARCH 14, 2011 FROM 18:40 TO 22:40

Proceedings of the International Topical Workshop on Fukushima Decommissioning Research, 2022, Vol.2022, p.1068

2022

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Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermal Hydraulics-Neutronics Coupling, and Stability Evaluation of ABWRs

Nuclear technology, 2007-05, Vol.158 (2), p.191-207

2007

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BWR Stability Issues in Japan

Science and technology of nuclear installations, 2008, Vol.2008 (2008), p.1-11

2008

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Stability Estimation of ABWR on the Basis of Noise Analysis

Journal of Power and Energy Systems, 2008, Vol.2(1), pp.421-434

2008

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Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 2

Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project

Analysis of muon radiography of the Toshiba nuclear critical assembly reactor

Development of the source term PIRT based on findings during Fukushima Daiichi NPPs accident

Update of the First TEPCO MAAP Accident Analysis of Units 1, 2, and 3 at Fukushima Daiichi Nuclear Power Station

Investigation of the status of Unit 2 nuclear reactor of the Fukushima Daiichi by Cosmic Muon Radiography

Study of the Unit-3 nuclear reactor of Fukushima Daiichi by cosmic muon radiography

Progress status and future issues of development of analysis and estimation technology for fuel debris characterization (2): Mid-and-Long term plan for accident investigation and progress status of samples obtained at the Fukushima Daiichi NPS

MAAP code analysis focusing on the fuel debris condition in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 2

Transient behaviour and heat transfer characteristics in debris beds: Simulation and analysis of the LIVEJ2 experiment

Validation and application of numerical modeling for in-vessel melt retention in corium pools

MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3

MAAP code analysis focusing on the fuel debris conditions in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 3

Comprehensive Analysis and Evaluation of Fukushima Daiichi Nuclear Power Station Unit 3

Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2

The Experimental and Simulation Results of LIVE-J2 Test-Investigation on Heat Transfer in a Solid-Liquid Mixture Pool

Inference of containment depressurization scenario of Fukushima Daiichi Nuclear Power Plant Unit-2 during the Morning of March 15th, 2011

Unsolved issues related to thermal-hydraulics in the suppression chamber during Fukushima Daiichi accident progressions

INTERACTION BETWEEN BWR FUEL CLADDING AND FUEL COMPONENTS IN EARLY PHASE OF SEVERE ACCIDENT

ESTIMATION OF THE RELATIONSHIP BETWEEN THE PCV->R/B GAS-LEAK MECHANISM AND THE HYDROGEN EXPLOSION IN 1F3

RECENT FINDINGS FROM FUKUSHIMA DAIICHI UNIT 1 PRIMARY CONTAINMENT VESSEL INVESTIGATIONS

EVALUATION OF TEMPERATURE AND HYDROGEN/WATER VAPOR RATIO IN 1F2 CORE ON MARCH 14, 2011 FROM 18:40 TO 22:40

Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermal Hydraulics-Neutronics Coupling, and Stability Evaluation of ABWRs

BWR Stability Issues in Japan

Stability Estimation of ABWR on the Basis of Noise Analysis

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