Plenary Lecture #1
Date & Time: Sept. 25 (Mon), 8:45 a.m.– 9:45 a.m.
Room: Grand Station II
“Confidence in Nuclear Safety under Uncertainties and Unknowns”
Akira Yamaguchi
The University of Tokyo
Dr. Yamaguchi is a Professor in the University of Tokyo, Nuclear Professional School, Graduate School of Engineering. He has received Ph.D degree in the nuclear engineering from the University of Tokyo in 1984. He joined the Power Reactor and Nuclear Fuel Development Corporation (currently Japan Atomic Energy Agency) and involved in the thermal-hydraulic and safety research of sodium cooled fast breeder reactor. In April of 2005, he moved to Osaka University, Department of Energy an Environment where he performed nuclear thermal-hydraulics, safety and risk assessment studies. Since January of 2015, he is Professor of the University of Tokyo. He has more than 30 years of experience in nuclear engineering. He has been a member of governmental committees on atomic energy policy, nuclear safety, nuclear regulation and nuclear science and technology by the METI, NRA and MEXT. Among them, he chairs the Nuclear Science and Technology Committee of the MEXT and Nuclear Safety, Technology and Human resource Development Committee of the METI. Currently he is the chair of the Risk Technology Committee of the Atomic Energy Society of Japan and a International Board member of the IAPSAM (International Association of PSA and Management).

The accident in Fukushima Dai-ichi Nuclear Power Plant Station in March 2011 is a remarkable event in the Japanese history of industrial and academic use of nuclear science and technology. The lessons-learned need to be deeply understood and reflected in facilities and activities related to nuclear energy use in Japan and to be shared with the international nuclear community.
It has raised several contradictory paradoxes. It should not be allowed to let an unknown left unresolved; we have recognized there always remain unknowns even after all possible measures have been implemented. If and only if one ensures a nuclear power plant is safe, its restart of commercial operation is accepted; even though a nuclear power plant is in conformity with the regulatory requirements, it is not sufficiently safe. The most interesting notion for us is probably related to the use of the probabilistic risk assessment (PRA). The PRA is very useful for improving safety and ensuring safety; the PRA is only applicable to limited use as the technology and data are incomplete and immature.
Like this, ensuring nuclear safety is a complicated and contradictory notion. Currently five nuclear power plants are in operation in Japan. It seems however, public does not trust the current practice of ensuring nuclear safety and protecting public and environment. Do we use PRA insights in dialog and communication with public? Do we rely on the PRA for ensuring nuclear safety? The PRA is the best available approach to identify and understand uncertainties and unknowns and is a key technology to answer to the complicated and contradictory question. The author believes ensuring nuclear safety implies thorough awareness of uncertainties and unknowns. As a consequence, it is justified and rationalized to continue safety enhancement activities for a nuclear power plant that is already safe enough.


Plenary Lecture #2
Date & Time: Sept. 25 (Mon), 10:00 a.m. – 11:00 a.m.
Room: Grand Station II
“Safety Culture and the One Reactor At a Time Mindset”
Karl Fleming received his B.S. in Physics from Penn State University, Cum Laude in 1969 and his M.S. in Nuclear Science and Engineering at Carnegie-Mellon University in 1974. He has devoted his entire professional career of 45 years to the advancement and application of PRA technology in the nuclear, chemical, process, and aerospace industries. Following professional and executive level assignments at General Atomics, Pickard Lowe and Garrick, and ERIN Engineering and Research he established an independent consulting firm in 2001 and continues to be active in advancing PRA technology.
Mr. Fleming is an internationally recognized expert in the development and application PRA technology. He is a member of the ASME/ANS Joint Committee on Nuclear Risk Management, a co-author of the ASME/ANS PRA Standard, a principal author of the ASME/ANS PRA Standard for Advanced non-LWRs, as well as hundreds of reports, papers, and peer reviewed articles on the development and application of PRA technology to nuclear reactor safety. His 45 years of experience includes more than 30 years in light water reactor (LWR) PRA technology, more than 15 years in high temperature gas-cooled reactor (HTGR) PRA, and extensive experience in applying PRA technology to the aerospace, process, and chemical industries. He was selected by the Advisory Committee on Reactor Safeguards to advise them on technical issues in the advancement of risk-informed decision making. He has given numerous presentations to the ACRS and participated in Commissioner briefings.
His contributions to PRA technology include the development of methods for common cause failure analysis in PRA such as the beta factor, Multiple Greek Letter, and contributing author of the Alpha Factor method, methods for predicting the reliability of piping systems and the influence of inspections, internal fire and internal flooding PRA, PRA of events initiated during low power and shutdown, PRA of multi-unit accidents, PRA database development, probabilistic treatment of severe accident phenomena in Level 2 PRA, and risk-informed applications.
Mr. Fleming’s recent contributions include development of an approach to estimate location dependent loss of coolant accident frequencies, co-author of EPRI reports on PRA guidelines and piping system failure rates for internal flooding PRA, and development of methods for evaluating seismically induced multi-unit accidents. He is the principal author of the IAEA Safety Series Report on the Technical Approach to Multi-unit PSA and a contributing author to IAEA TECDOC-1511 and 1804 on technical attributes for PSA Applications.


Plenary Lecture #3
Date & Time: Sept. 25 (Mon), 11:00 a.m. – 12:00 p.m.
Room: Grand Station II
“Computational Risk Assessment”
Curtis Smith, Ph.D., is a Directorate Fellow in the Risk Assessment and Management Services Department at Idaho National Laboratory. In this capacity, he is the past project manager for the NRC’s SAPHIRE risk analysis software, serves as a lead instructor and manager for the NRC’s Risk Assessment Training program, is a technical lead for the NASA Safety Mission Success project at INL, and is the Risk Informed Safety Margins Characterization Pathway (RISMC) lead under the DOE Light Water Reactor Sustainability Program.
Dr. Smith has been in the risk and reliability assessment field for more than 25 years. He has worked at INL as a risk analysis specialist and has served as a consultant for a diverse set of organizations including the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC), the National Aeronautics and Space Administration (NASA), the International Atomic Energy Agency (IAEA), the Federal Aviation Administration (FAA), and other government and private companies. He also was a visiting scientist to the OECD-sponsored Halden Reactor Project, performing human performance-related research, was the Chair of the ASME Safety Engineering and Risk Analysis (SERAD) Executive Committee, is currently on the Board for the International Association of Probabilistic Safety and Management (IAPSAM) organization, and is a past President of the Idaho State University College of Engineering Advisory Council (EAC). Dr. Smith has published over 200 papers, books, and reports on risk and reliability theory and application. He has taught over 100 technical and university courses on a variety of reliability and safety topics. He holds a Ph.D. in nuclear engineering from Massachusetts Institute of Technology. He is a member of the American Society of Mechanical Engineers, American Nuclear Society, and the Idaho Academy of Sciences.


Plenary Lecture #4
Date & Time: Sept. 26 (Tue), 8:00 a.m. – 9:00 a.m.
Room: Grand Station II
“PRA Community Support for Delivery of the Nuclear Promise””
Roy Linthicum is the chair of the Risk Management Committee for the PWR Owners’ Group. He has over 30 years Nuclear PRA experience, primarily related to Risk-Informed Applications. Roy has been involved with MSPI and the NEI ROP Task Force since the original MSPI pilot efforts and is a participating member in multiple NEI Risk Related Task Forces. He is also involved in the Risk Informed Operations team for Delivering the Nuclear Promise. Roy has been employed by Exelon Generation for since 1999 with previous positions at Sargent & Lundy, Public Service Electric and Gas, Arizona Public Service, Northeast Utilities and Knolls Atomic Power Laboratory. Roy is a graduate of Rensselaer Polytechnic University with a degree in nuclear.


Plenary Lecture #5
Date & Time: Sept. 27 (Wed), 8:00 a.m. – 9:00 a.m.
Room: Grand Station II
“PRA R&D – Changing the Way We Do Business?”
Nathan Siu is a Senior Technical Adviser for PRA (Probabilistic Risk Assessment) Analysis in the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission (NRC). He has over 35 years of experience in the development and application of PRA methods, models, and tools and has co-authored over 200 papers and reports. At the NRC, he’s responsible for providing PRA-related advice and support regarding technical programs and issues (including issues requiring research and development) and cooperative activities with U.S. and international organizations. He is also currently involved in broader, strategic discussions regarding the role, performance, and effectiveness of regulatory research at the NRC. He is a past-chair of the OECD/NEA Working Group on Risk Assessment, a Fellow Member of the American Nuclear Society, and a past-member of the International Association for Probabilistic Safety Assessment (IAPSAM) Board of Directors. Prior to joining NRC in 1997, he was on the Idaho National Engineering Laboratory staff (1992-1997), the Nuclear Engineering Department faculty at the Massachusetts Institute of Technology (1986-1992), and the staff of Pickard, Lowe, and Garrick, Inc. (1980-1986). He received his B.S., M.S., and Ph.D. degrees at the University of California at Los Angeles.