Name MUTA Hitoshi
Official Title Associate Professor
Affiliation Nuclear Safety Engineering
Profile He is a chief researcher of nuclear safety engineering department, Japan Nuclear Energy Safety Organization (JNES), which is a technical support organization for Japanese regulatory body.
He received the Dr. Eng. degree in System Safety Engineering from graduate school of Tokyo University of Marine Science and Technology on 2010.
His research interests include system reliability, risk assessment of nuclear power plant and risk-informed regulation.
Research Field(Keyword & Summary)
  1. (1) Probabilistic Risk Assessment

    This research area aims to assess the risk of Nuclear Power Plants and Nuclear Facilities expressed as Core Damage Frequency, Containment Failure Frequency and Public Exposure Risk combined with Consequence or Impact. Mainly the assessment process for the external events such as earthquake, tsunami and any kinds of natural disaster and the combination of these events, are the research theme, as well as dynamic modeling of these kinds of events and subsequent accident scenarios.

  2. (2) Security against external threats and scientifically rational risk management

    To pursue safety measures against external threats, including natural phenomena with large uncertainties such as earthquakes and tsunamis, and to study scientifically rational safety assurance and crisis management, such as measures to prevent serious accidents and disaster prevention measures, using probabilistic risk assessment methods.

Representative Papers
  1. (1) “Development of interaction model on the risk assessment method for nuclear facilities considering impact of external natural hazard”, Journal of Nuclear Science and Technology, Published online: 14 Dec 2020
  2. (2) “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-, Springer, 978-4-431-55820-0, pp. 137-153, January 2016
  3. (3) “Quantitative Modeling of Digital Reactor Protection System Using Markov State-Transition Model”, Journal of Nuclear Science and Technology, JNST Vol. 51, Issues 9-10, pp.1073-1086, September 2014
  4. (4) “Functional Safety Assessment of Safety-Related Systems with Non-perfect Proof-tests”, IEICE Transactions on Fundamentals of Electronics, Communications and Computer Sciences, IEICE, Vol. E97-A, No. 8, pp.1739-1746, August 2014.
  5. (5) Proposal of Evaluation Methodology of Multiple-Failure Initiating Events for Seismic PRA, Transactions of Atomic Energy Society of Japan, Vol.16, No.2, p.89-99, 2017.
  6. (6) Proposal of Methodology of Tsunami Accident Sequence Analysis Induced by Earthquke Using DQFM Methodology, Transactions of Atomic Energy Society of Japan, Vol.16, No.1, p.49-56, 2017.
  7. (7) Study of Thermal Hydraulic Behaviors during Multiple Steam Generator Tube Rupture Events in PWR, Transactions of Atomic Energy Society of Japan, Vol.15, No.3, p.159-172, 2016.
  8. (8) Proposal of PRA Methodology Considering State Transitions and Time-dependent Failure Rates of Components, Transactions of Atomic Energy Society of Japan, Vol.15, No.2, p.70-83, 2016.
  9. (9) Application of Markov State-Transition Model to Reliability Analysis of 2-out-of-4 Reactor Trip System, Transactions of Atomic Energy Society of Japan, Vol.14, No.1, p.25-39, 2015.
  10. (10) “Basic concept of a near future BWR,” Nuclear Engineering and Design, Elsevier, Volume 230, Issues 1–3, pp.181–193, May 2004.
  1. N/A
Grant-in-Aid for Scientific Research Support: Japan Society for Promotion of Science (JSPS)
Recruitment of research assistant(s) No
Affiliated academic society (Membership type) (1) Atomic Energy Society of Japan (Menber)
(2) IEICE (Menber)
(3) ASME (Menber)
Education Field (Undergraduate level) Nuclear Safety Engineering, Probabilistic Risk Assessment, Nuclear Risk Management.
Education Field (Graduate level) Advanced Nuclear Safety, Advaned Nuclear Seismic Safety and Risk Engineering.