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Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior

Nuclear engineering and design, 2021-11, Vol.383, p.111426, Article 111426

Sato, Ikken

2021

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An interpretation of Fukushima-Daiichi Unit 3 plant data covering the two-week accident-progression phase based on correction for pressure data

Journal of nuclear science and technology, 2019-05, Vol.56 (5), p.394-411

Sato, Ikken

2019

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Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis

Nuclear engineering and design, 2021-05, Vol.376, p.111123, Article 111123

2021

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Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3

Nuclear engineering and design, 2021-08, Vol.379, p.111244, Article 111244

2021

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Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis

Journal of nuclear science and technology, 2021-04, Vol.58 (4), p.434-460

2021

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Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident

Annals of nuclear energy, 2021-01, Vol.150, p.107819, Article 107819

2021

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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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Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3

Mechanical Engineering Journal, 2022, Vol.9(2), pp.21-00436-21-00436

2022

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Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Journal of nuclear engineering and radiation science, 2020-04, Vol.6 (2)

2020

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Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors

Nuclear engineering and design, 2012-08, Vol.249, p.212-227

2012

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Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Journal of nuclear science and technology, 2011-01, Vol.48 (4), p.556

2011

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Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Journal of nuclear science and technology, 2011-04, Vol.48 (4), p.556-566

2011

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Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case

Nuclear engineering and design, 2008, Vol.238 (1), p.66-73

2008

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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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Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors

Journal of nuclear science and technology, 2014-09, Vol.51 (9), p.1114-1124

2014

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Fuel Pin Behavior up to Cladding Failure under Pulse-Type Transient Overpower in the CABRI-FAST and CABRI-RAFT Experiments

Journal of nuclear science and technology, 2010-04, Vol.47 (4), p.396

2010

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Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3

Annals of nuclear energy, 2019-11, Vol.133, p.21-34

2019

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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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Post-Test Analyses of the CMMR-4 Test

Journal of nuclear engineering and radiation science, 2022-04, Vol.8 (2)

2022

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Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2

Annals of nuclear energy, 2021-09, Vol.160, p.108430, Article 108430

2021

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The result of a wall failure in-pile experiment under the EAGLE project

Nuclear engineering and design, 2007-11, Vol.237 (22), p.2165-2174

2007

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Measurement of Doppler broadening of prompt gamma-rays from various zirconium- and ferro-borons

Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2021-03, Vol.991, p.164964, Article 164964

2021

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Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors

Journal of nuclear science and technology, 2011-02, Vol.48 (2), p.188-204

2011

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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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Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior

An interpretation of Fukushima-Daiichi Unit 3 plant data covering the two-week accident-progression phase based on correction for pressure data

Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis

Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3

Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis

Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident

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

Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors

Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case

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

Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors

Fuel Pin Behavior up to Cladding Failure under Pulse-Type Transient Overpower in the CABRI-FAST and CABRI-RAFT Experiments

Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3

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

Post-Test Analyses of the CMMR-4 Test

Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2

The result of a wall failure in-pile experiment under the EAGLE project

Measurement of Doppler broadening of prompt gamma-rays from various zirconium- and ferro-borons

Three-Pin Cluster CABRI Tests Simulating the Unprotected Loss-of-Flow Accident in Sodium-Cooled Fast Reactors

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

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