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Application of reinforcement learning to deduce nuclear power plant severe accident scenario

Annals of nuclear energy, 2024-09, Vol.205, p.110605, Article 110605

2024

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A review of the assessment of severe accident management guidelines and actions through analytical simulations

Annals of nuclear energy, 2023-01, Vol.180, p.109448, Article 109448

2023

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SEVERE ACCIDENT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT AND IMPROVEMENTS SUGGESTED

Nuclear Engineering and Technology, 2014, 46(2), , pp.207-216

2014

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Numerical assessment for entry condition of severe accident management guidelines in a Swedish nuclear power plant

Annals of nuclear energy, 2022-05, Vol.169, p.108969, Article 108969

2022

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Optimized initiation criterion for a filtered containment venting in case of a severe accident in a nuclear power plant

Nuclear engineering and design, 2022-05, Vol.391, p.111729, Article 111729

2022

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Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident

Nuclear engineering and technology, 2022-12, Vol.54 (12), p.4534-4550

2022

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Estimation of the likelihood of severe accident management decision-making using a fuzzy logic model

Annals of nuclear energy, 2020-09, Vol.144, p.107581, Article 107581

2020

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Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code

Nuclear engineering and design, 2020-04, Vol.359, p.110452, Article 110452

2020

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Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code

Nuclear engineering and design, 2020-03, Vol.358, p.110443, Article 110443

2020

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iROCS: Integrated accident management framework for coping with beyond-design-basis external events

Nuclear engineering and design, 2016-03, Vol.298, p.1-13

2016

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Fundamental safety strategy against severe accidents on prototype sodium-cooled fast reactor

Journal of nuclear science and technology, 2016-11, Vol.53 (11), p.1774-1786

2016

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Evaluation of an accident management strategy using an emergency water injection in a reference PWR SFP

Annals of nuclear energy, 2018-03, Vol.113, p.353-379

2018

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Cost per severe accident as an index for severe accident consequence assessment and its applications

Reliability engineering & system safety, 2014-03, Vol.123, p.110-122

2014

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Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1

Progress in nuclear energy (New series), 2023-04, Vol.158 (C), p.104609, Article 104609

2023

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Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

Nuclear Engineering and Technology, 2015, 47(1), , pp.66-73

2015

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Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline

Progress in nuclear energy (New series), 2015-11, Vol.85, p.319-324

2015

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Canadian licensing framework of CANDU reactors and safety analysis challenges in the allocation of Emergency Mitigating Equipment

Progress in nuclear energy (New series), 2020-09, Vol.127, p.103438, Article 103438

Torabi, Keivan

2020

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Consideration of decontamination model for severe accident consequence assessment

Journal of nuclear science and technology, 2015-11, Vol.52 (11), p.1402-1416

2015

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Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

Frontiers in Energy, 2021-12, Vol.15 (4), p.872-886

2021

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Review of Severe Accident Phenomena in LWR and Related Severe Accident Analysis Codes

Research journal of applied sciences, engineering and technology, 2013-04, Vol.5 (12), p.3320-3335

2013

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SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments

Annals of nuclear energy, 2015-03, Vol.77, p.376-392

Fukano, Yoshitaka

2015

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Synthesis of the ASTEC integral code activities in SARNET – Focus on ASTEC V2 plant applications

Annals of nuclear energy, 2014-12, Vol.74 (C), p.224-242

2014

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Application of moving particle semi-implicit method on simulating melt spreading within OECD/ROSAU project

Nuclear engineering and design, 2024-10, Vol.427, p.113447, Article 113447

2024

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Human Factors Engineering Analysis for Human System Interface of Severe Accident Management Support System Based on Human Factors Engineering Program

Advances in Human Error, Reliability, Resilience, and Performance, 2019, Vol.956, p.131-141

2019

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Improvement of the European thermodynamic database NUCLEA

Progress in nuclear energy (New series), 2010, Vol.52 (1), p.84-96

2010

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Application of reinforcement learning to deduce nuclear power plant severe accident scenario

A review of the assessment of severe accident management guidelines and actions through analytical simulations

SEVERE ACCIDENT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT AND IMPROVEMENTS SUGGESTED

Numerical assessment for entry condition of severe accident management guidelines in a Swedish nuclear power plant

Optimized initiation criterion for a filtered containment venting in case of a severe accident in a nuclear power plant

Effect of mitigation strategies in the severe accident uncertainty analysis of the OPR1000 short-term station blackout accident

Estimation of the likelihood of severe accident management decision-making using a fuzzy logic model

Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code

Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code

iROCS: Integrated accident management framework for coping with beyond-design-basis external events

Fundamental safety strategy against severe accidents on prototype sodium-cooled fast reactor

Evaluation of an accident management strategy using an emergency water injection in a reference PWR SFP

Cost per severe accident as an index for severe accident consequence assessment and its applications

Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline

Canadian licensing framework of CANDU reactors and safety analysis challenges in the allocation of Emergency Mitigating Equipment

Consideration of decontamination model for severe accident consequence assessment

Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

Review of Severe Accident Phenomena in LWR and Related Severe Accident Analysis Codes

SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments

Synthesis of the ASTEC integral code activities in SARNET – Focus on ASTEC V2 plant applications

Application of moving particle semi-implicit method on simulating melt spreading within OECD/ROSAU project

Human Factors Engineering Analysis for Human System Interface of Severe Accident Management Support System Based on Human Factors Engineering Program

Improvement of the European thermodynamic database NUCLEA

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