| Published Papers |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date | DOI | Referee |
| 1 | Proposal of quantification method of dynamic system reliability model of digital RPS using Markov state-transition model | Journal of Nuclear Science and Technology | | | | | 2023 | https://doi.org/10.1080/00223131.2023.21693791 | |
| 2 | Development of interaction model on the risk assessment method for nuclear facilities using a system model with a multi-layer structure  | Journal of Nuclear Science and Technology | 58 | 5 | 542 | 566 | 2021 | https://doi.org/10.1080/00223131.2020.18458381 | Refereed |
| 3 | Evaluating the Seismic Diversity and Robustness of Nuclear Power Plants | Journal of Nuclear Science and Technology | 58 | 9 | 970 | 983 | 2021 | https://doi.org/10.1080/00223131.2021.18999941 | Refereed |
| 4 | Bayesian-estimation-based method for generating fragility curves for high-fidelity seismic probability risk assessment | Journal of Nuclear Science and Technology | 58 | 11 | 1220 | 1234 | 2021 | https://doi.org/10.1080/00223131.2021.19315171 | Refereed |
| 5 | Study on reliability of seismic capacity analysis for important equipment in nuclear facilities | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | 5 | | | | 2021 | https://doi.org/10.1115/PVP2021-617421 | Refereed |
| 6 | Research and examination of seismic safety evaluation and function maintenance for important equipment in nuclear facilities | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | 5 | | | | 2021 | https://doi.org/10.1115/PVP2021-617811 | Refereed |
| 7 | A framework of RI-PB seismic design/Part 4: - Case studies of accident sequence analysis considering seismic correlation | 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020 | | | 2452 | 2457 | 2020 | https://doi.org/10.3850/978-981-14-8593-0_5246-cd1 | |
| 8 | A Framework of RI-PB Seismic Design - Part 3: Accident Sequence Analysis Considering Seismic Correlation | 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020 | | | 2423 | 2428 | 2020 | https://doi.org/10.3850/978-981-14-8593-0_3767-cd1 | |
| 9 | A framework of RI-PB seismic design/Part 2: Evaluation of seismic diversity of SSCs focusing on response spectrum characteristics of ground motion | 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020 | | | 2417 | 2422 | 2020 | https://doi.org/10.3850/978-981-14-8593-0_3722-cd1 | |
| 10 | Study on quantitative evaluation method of interaction multi-layer model for nuclear fuel facilities considering external natural hazard | 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020 | | | 2333 | 2340 | 2020 | https://doi.org/10.3850/978-981-14-8593-0_5713-cd1 | |
| 11 | A Framework of RI-PB seismic design/Part 1: Characteristics of the Proposed RI-PB seismic design | 30th European Safety and Reliability Conference, ESREL 2020 and 15th Probabilistic Safety Assessment and Management Conference, PSAM 2020 | | | 2411 | 2416 | 2020 | https://doi.org/10.3850/978-981-14-8593-0_3599-cd1 | |
| 12 | Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering | Journal of Nuclear Science and Technology | 56 | 5 | 367 | 368 | May. 4, 2019 | https://doi.org/10.1080/00223131.2019.15888021 | Refereed |
| 13 | Study on PRA procedure considering combination of multiple events using DQFM methodology | International Conference on Nuclear Engineering, Proceedings, ICONE | 2 | | | | 2018 | https://doi.org/10.1115/ICONE26-820861 | |
| 14 | Proposal of methodology of tsunami accident sequence analysis induced by earthquake using DQFM methodology | Transactions of the Atomic Energy Society of Japan | 16 | 1 | 49 | 56 | 2017 | https://doi.org/10.3327/taesj.J16.0191 | Refereed |
| 15 | Probabilistic risk assessment method development for high temperature gas-cooled reactors (2) development of accident sequence analysis methodology | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | | | | | 2017 | | |
| 16 | Probabilistic risk assessment method development for high temperature gas-cooled reactors (1) project overviews | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | | | | | 2017 | | |
| 17 | Methodology of treatment of multiple failure initiating events for seismic PRA (1) establishment of analysis methodology and trial analysis of core damage frequency | International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017 | 1 | | 68 | 73 | 2017 | | |
| 18 | Methodology of treatment of multiple failure initiating events for seismic PRA (2)success criteria analysis for multiple pipe break accidents of a PWR | International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017 | 1 | | 92 | 99 | 2017 | | |
| 19 | Proposal of evaluation methodology of multiple-failure-initiating events for seismic PRA | Transactions of the Atomic Energy Society of Japan | 16 | 2 | 89 | 99 | 2017 | https://doi.org/10.3327/taesj.J16.0131 | Refereed |
| 20 | Development of a new mathematical framework for seismic probabilistic risk assessment for nuclear power plants – plan and current status – | Earthquakes, Tsunamis and Nuclear Risks: Prediction and Assessment Beyond the Fukushima Accident | | | 137 | 153 | Jan. 1, 2016 | https://doi.org/10.1007/978-4-431-55822-4_111 | Refereed |
| 21 | Study of thermal hydraulic behaviors during multiple steam generator tube rupture events in PWR | Transactions of the Atomic Energy Society of Japan | 15 | 3 | 159 | 172 | 2016 | https://doi.org/10.3327/taesj.J15.0051 | Refereed |
| 22 | Proposal of PRA methodology considering state transitions and time-dependent failure rates of components | Transactions of the Atomic Energy Society of Japan | 15 | 2 | 70 | 83 | 2016 | https://doi.org/10.3327/taesj.J15.0041 | Refereed |
| 23 | Application of Markov state-transition model to reliability analysis of 2-out-of-4 reactor trip system | Transactions of the Atomic Energy Society of Japan | 14 | 1 | 25 | 39 | 2015 | https://doi.org/10.3327/taesj.J14.0111 | Refereed |
| 24 | Functional safety assessment of safety-related systems with non-perfect proof-tests | IEICE Transactions on Fundamentals of Electronics, Communications and Computer Sciences | E97-A | 8 | 1739 | 1746 | 2014 | https://doi.org/10.1587/transfun.E97.A.17391 | Refereed |
| 25 | Quantitative modeling of digital reactor protection system using Markov state-transition model | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 51 | 9 | 1073 | 1086 | 2014 | https://doi.org/10.1080/00223131.2014.9063311 | Refereed |
| 26 | Functional Safety Assessment of the Safety Instrumented Systems with Multiple Sub-safety Functions | JSSE | 49 | 2 | 94 | 103 | Apr. 15, 2010 | https://doi.org/10.18943/safety.49.2_941 | Refereed |
| 27 | Basic concept of a near future BWR | NUCLEAR ENGINEERING AND DESIGN | 230 | 1-3 | 181 | 193 | May. 2004 | https://doi.org/10.1016/j.nucengdes.2003.11.0231 | Refereed |
| MISC |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date |
| 1 | Research on Seismic Correlation for PRA: Part 2: DQFM using correlated random numbers based on the concept of common and independent variability of response factors | 日本原子力学会春の年会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 2 | A study on the effectiveness of floor isolation considering seismic diversity | The Proceedings of the Dynamics & Design Conference | 2021 | | 210 | | 2021 |
| 3 | For Better Understanding of PRA - Guidance for Better Usage and Application of PRA (2): Risk and Uncertainty | Journal of the Atomic Energy Society of Japan | 62 | 7 | 385 | 388 | 2020 |
| 4 | Establishment of Risk Science and Technology Division and its Significance | Journal of the Atomic Energy Society of Japan | 61 | 4 | 335 | 336 | 2019 |
| 5 | 2B09 Development of a Human Resources for Nuclear Engineering in Tokyo City University:Programs in Safety Engineering and Teaching Effectiveness in Cooperative Major in Nuclear Engineering | Proceedings of Annual Conference of JSEE | 2017 | 0 | 188 | 189 | 2017 |
| 6 | Overturning prevention mechanism with frictional sliding for light-weight mechanical structure in seismic input (Examination of fundamental design specification and performance verification test) | Transactions of the JSME (in Japanese) | 82 | 842 | 16-00184 | 16-00184 | 2016 |
| 7 | Treatment of Non-perfect Proof-tests in Functional Safety Assessment | IEICE technical report | 113 | 490 | 17 | 20 | Mar. 13, 2014 |
| 8 | Functional Safety Assessment of SIS performing Multiple Safety Functions | IEICE technical report | 110 | 346 | 1 | 4 | Dec. 10, 2010 |
| 9 | Infrastructure Development of Level 1 PSA for Internal Events in JNES = Initiating Events and Uncertainty Analysis Method considering SOKC = | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010f | | 489 | 489 | 2010 |
| 10 | Parameter Estimation Using The Hierarchical Bayes Method. | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009f | | 390 | 390 | 2009 |
| 11 | Functional Safety of Safety Related Systems with Safe Shutdown | IEICE technical report | 107 | 385 | 15 | 18 | Dec. 7, 2007 |
| 12 | Development of Risk-based Maintenance Support System | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2006s | | 289 | 289 | 2006 |
| Conference Activities & Talks |
| No. | Ｔitle | Conference | Publication date | Promoter | Venue |
| 1 | Methodology of treatment of multiple failure initiating events for seismic PRA (2)success criteria analysis for multiple pipe break accidents of a PWR | International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017 | Jan. 1, 2017 | | |
| 2 | Methodology of treatment of multiple failure initiating events for seismic PRA (1) establishment of analysis methodology and trial analysis of core damage frequency | International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017 | Jan. 1, 2017 | | |
| 3 | Probabilistic risk assessment method development for high temperature gas-cooled reactors (1) project overviews | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | Jan. 1, 2017 | | |
| 4 | Probabilistic risk assessment method development for high temperature gas-cooled reactors (2) development of accident sequence analysis methodology | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | Jan. 1, 2017 | | |
| 5 | Treatment of Non-perfect Proof-tests in Functional Safety Assessment | IEICE technical report | Mar. 13, 2014 | | |
| 6 | The basic idea of quantitative model of reactor protection system considering stochastic process | PSAM 2014 - Probabilistic Safety Assessment and Management | Jan. 1, 2014 | | |
| 7 | The effects of considering SOKC for uncertainty analyses and psa model developing strategy | 11th International Probabilistic Safety Assessment and Management Conference and the Annual European Safety and Reliability Conference 2012, PSAM11 ESREL 2012 | Dec. 1, 2012 | | |
| 8 | Development of core damage frequency evaluation code for NPP due to components aging degradation | International Topical Meeting on Probabilistic Safety Assessment and Analysis 2011, PSA 2011 | Aug. 29, 2011 | | |
| 9 | Functional Safety Assessment of SIS performing Multiple Safety Functions | IEICE technical report | Dec. 10, 2010 | | |
| 10 | Infrastructure Development of Level 1 PSA for Internal Events in JNES = Initiating Events and Uncertainty Analysis Method considering SOKC = | Proceedings of AESJ | 2010 | | |
| 11 | Parameter Estimation Using The Hierarchical Bayes Method. | Proceedings of AESJ | 2009 | | |
| 12 | Functional safety of safety related systems with safe shutdown | 9th International Conference on Probabilistic Safety Assessment and Management 2008, PSAM 2008 | Dec. 1, 2008 | | |
| 13 | Functional Safety of Safety Related Systems with Safe Shutdown | IEICE technical report | Dec. 7, 2007 | | |
| 14 | Functional Safety of Safety Related Systems with Safe Shutdown | IEICE technical report | Dec. 7, 2007 | | |
| 15 | A risk-monitoring system hybridized of that for outage-plan management | Proceedings of the 8th International Conference on Probabilistic Safety Assessment and Management, PSAM 2006 | Dec. 1, 2006 | | |
| 16 | Development of Risk-based Maintenance Support System | Proceedings of AESJ | 2006 | | |
