Mike Modro (NINE, Italy)
Vice President for Strategy Development
Nuclear Industrial and Engineering
Mr. Mike Modro has over 40 years of experience in research and engineering, including over 30 years in Nuclear Reactor Design, Licensing and Safety Research. His field of expertise includes: Analyses and Research related to Nuclear Power Plant behavior during accident conditions; Assessment and Validation of various Computer Codes used to simulate nuclear plant behavior; Development and conduct of Experimental programmes in support of nuclear safety needs; Programme and line Management, Business and Resource development. He worked over 25 years within the Idaho National Laboratory (United States) and 6 years as Senior Safety Assessment Officer for the International Atomic Energy Agency (for whom he is currently a Senior Consultant). He is a Guest Lecturer for the Imperial College of London (UK). He has a background in Physics from the University of Bern (Switzerland) and the University of Warsaw (Poland).
Dan Gabriel Cacuci (USC, USA)
SC SmartState Endowed Chair Professor of Nuclear Engineering
University of South Carolina
He has recently been named chair of the SmartState Center of Economic Excellence in Nuclear Energy Science and Engineering. He believes in it fully and thinks it is an unusually staunch commitment to recognize openly that nuclear energy has been, and will continue to be, an irreplaceable contributor to the energy mix of the U.S. and the world.
Professor Kostadin Ivanov has been working in the Nuclear field for over 34 years. His field of expertise includes: Reactor Physics; Methods in Static and Dynamic Analysis; Nuclear Power Plant Modeling and Safety; Fuel Management and Core Design; Verification and Validation of Multi-Physics simulations. He has worked over ten years for the Pennsylvania State University as Distinguished Professor including Graduate Coordinator of Nuclear Engineering Programme, and for two years as Visiting Professor at the Karlsruhe Institute of Technology, Department of Mechanical Engineering, in Germany. Since 2015 he is Professor and Department Head of the Department of Nuclear Engineering at the North Carolina State University (USA).
He was and currently is in charge as leading scientist of several international benchmarks organized under the umbrella of the Nuclear Energy Agency (NEA).
His work has been published on hundreds of academic and international journals and conference proceedings. He holds a PhD in Reactor Physics from the Bulgarian Academy of Science.
Mr. Scott a Senior Vice President – Deputy, Global I&C Business Unit for Framatome is responsible for the global P&L within the group and a global footprint of more than 1300 staff. Recently, Mr. Scott was the responsible architect that drove an important M&A of the Schneider Electric Global Nuclear I&C Business to Framatome.
Formally, Senior Vice President and the Chief Nuclear Officer for Schneider Electric, responsible for the company’s global nuclear organization, P&L, verification and validation; licensing and compliance; quality assurance; sales, marketing and business development at offices and facilities in North America, Europe/MENA and Asia. Recently responsible for one of the largest Digital Control Room efforts in nuclear, delivering eight new units in China - consisting of Control Room Design and all of the Safety and Non-Safety Controls Systems. With seven of the units connected to grid late 2014 and mid-2015. Last unit to go online in fall 2017.
Mr. Scott was the General Chair of American Nuclear Society’s NPIC & HMIT 2017 conference
He has more than 38 years’ experience in managing nuclear utility contracts globally, including vast expertise in licensing and compliance; Mergers & Acquisitions; electrical and controls design; both in startup and operation. Before accepting this position, Scott served as the Vice President of Invensys’s nuclear business in North America, responsible for business development, strategy, risk management, nuclear procedures and governance, delivery execution. Before joining Invensys, he was President of CRS Engineering, a multi-discipline engineering and design-consulting firm. In that position, he provided business development consulting to clients in the global nuclear space, as well as provided strategic marketing analysis, project evaluation and design and digital architecture services with a focus in the global utilities market.
Dr Alessandro Petruzzi is President of the Board of Directors of Nuclear and INdustrial Engineering (NINE) since 2011. He received Ph.D. in Nuclear and Industrial Safety from University of Pisa where he worked on development of Uncertainty Methods for system thermal-hydraulics codes and application of BEPU methodology to Safety Analysis in Licensing framework. From 2007 to 2013 he acted as deputy manager of GRNSPG (University of Pisa) working on the preparation of Chapter 15 of FSAR of Atucha-2 NPP in Argentina. His current research concentrates on thermal-hydraulics, multi-physics methods for reactor safety analysis, forward and inverse methods for uncertainty quantification and he is member of several NEA working group both at NSC and CSNI. In 2013 he was the main organizer of NURETH-15 in Pisa.
Dr. Greg Rzentkowski joined the IAEA as Director of Nuclear Installation Safety in 2015.
Greg has over 35 years of experience in mechanical and nuclear engineering. He began his nuclear career in 1989 in Ontario Hydro, Canada, as a Senior Research Engineer. Since joining the Canadian Nuclear Safety Commission in 1995, he has held progressively responsible positions in management of technical and regulatory programs. In 2008, he was named Director General of the Directorate of Power Reactor Regulation. He also chaired the Fukushima Task Force which developed Canada’s action plan for implementation of safety improvements.
Greg holds a Doctor of Philosophy in Mechanical Engineering and has served as Adjunct Professor at McMaster University in Hamilton, Canada. He published several research papers in scientific journals and conference proceedings, and proprietary reports prepared for the Nuclear Industry.
Dr. Christophe Schneidesch joined TRACTEBEL in 1992 where he has been in charge of the development, the qualification and the deployment of 3D core physics code packages and the related methodologies for core reload studies and safety analyses for more than 10 years. In 2005, he became manager of the Core and Fuel Studies Group of TRACTEBEL, responsible of all core-physics activities related to the fuel cycle, core design, safety evaluation and core operational support for the Belgian Utility. In parallel to his production activities, he is deeply involved in the development, the qualification and the licensing of the codes and methodologies necessary for the missions of his group. His current focus lies on multi-physics codes and methods for PWR plant transient analysis and the deployment of BEPU approaches for a better identification and quantification of uncertainties in safety demonstration and operational support. His work is connected to his participations to several NSC/NEA working groups. Physicist Engineer and M. in Nuclear Engineering from University of Louvain-la-Neuve (UCL), Belgium, he graduated as M.Sc. at Thayer School of Engineering, USA, and received his Dr. in Mechanical Engineering from UCL in 1992.
In 1991, Deog-Yeon Oh got a PhD degree in the department of nuclear engineering from the Korea Advanced Institute of Science and Technology (KAIST), Korea.
After graduation, he had worked for the Korea Atomic Energy Research Institute (KAERI) from 1991 to 1996 in the department of core protection system analysis. Under British Council scholarship, he has studied the failure detection of sensors in Oxford University as a visiting scholar for one year from 1996. And then, he transferred to KNF (KEPCO Nuclear Fuel Corporation), and has worked to design the core protection system and monitoring system until 2000. In 2000, he joined in the KINS (Korea Institute of Nuclear Safety) and now, in the department of Reactor Safety Evaluation of KINS, he performs the licensing review of the safety analysis, especially for Loss-of-Coolant Accident (LOCA), and the associated research work including Best-Estimated method and uncertainty quantification. In addition, he has actively participated in the national and international nuclear conference, and international research program resulting in good achievements.
He is proud of a variety of nuclear experience for design, research, and regulatory review in nuclear safety area.
Dr. Timothy E. Valentine is the director of the Radiation Safety Information Computational Center (RSICC) As director of RSICC, he is responsible directing and expanding the services and operations of the center as well as being responsible for international collaborations with the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD-NEA) as well as Japanese Research Organization for Information Science and Technology (RIST). Dr. Valentine has twice served as a science and nuclear policy advisor in the U.S Senate on the Committee on Energy and Natural Resources and for Senators Bingaman and Alexander. Dr. Valentine has held various line, program management and technical research positions with a focus on energy R&D and nuclear safety, security and nonproliferation.
Peter Hughes’ nuclear safety career has spanned 4 decades and has included 16 years in the nuclear industry UK (NPP operations, design, construction), and Canada (NPP consultancy), and 24 years as a UK nuclear regulator. His EC&I specialism, coupled with his experience in probabilistic safety analysis led him to develop expertise in safety cases for reactor computer-based safety systems. He led the expert group that developed the IAEA Safety Guide I&C Systems Important to Safety in NPPs.
He has also worked at IAEA on two occasions firstly as Scientific Secretary to Nuclear Safety Standards Committee and in his most recent role at IAEA, as Section Head for Safety Assessment Section. He was a key player in delivering the IAEA Fukushima Action Plan, and led the organising of the IAEA’s first International Expert Meeting on Reactor and Spent Fuel Safety in March 2012, supporting the organising of follow-on conferences on Defence in Depth in 2013 and Severe Accident Management in 2014. His major contribution was as an IAEA co-chair on the IAEA Director General's team where he led the writing and editing of Technical Volume 2 Safety Assessment that reported on the causes of the accident at the Fukushima Nuclear Power Station and explained why the accident occurred the way it did.
In 2016 he took early retirement from the UK nuclear regulatory body (ONR). In his last role he was Head of Safety Analysis for the Generic Design Assessment of the UK-AP1000 and UK-ABWR. He now runs a successful nuclear safety and regulatory consultancy advising a number of international clients.
Mr. Quinn has over 40 years of experience in managing nuclear and fossil utility contracts and personnel in support of both project and supplemental assignments at various utilities in the U.S. He is past President of the American Nuclear Society (ANS) (1998-1999) and currently serves as the Chairman of the International Electrotechnical Commission (IEC) SC45A Working Group A9 on Nuclear Instrumentation Systems. He has managed and performed projects in licensing and compliance, electrical and controls design, startup and operation, including Standards development for the Instrument Society of America (ISA) and the International Electrotechnical Commission (IEC) and is the author of over 100 papers and presentations on nuclear instrumentation and control subjects. He has been an instructor at the MIT Summer Reactor Safety Course for over 15 years, the NRC Digital I&C Licensing Course for 6 years, a number of IAEA country I&C training courses, and a Board member of the nuclear engineering programs at both Oregon State and The Ohio State University. He currently provides licensing support to TerraPower for their Instrumentation and Control Program, in 2013 completed the licensing and engineering for eight awarded IOM nuclear projects in China, and was a team member for the Diablo Canyon Plant Protection System Replacement Project License Amendment, which received NRC approval in December, 2016. In 2009, he was awarded the highest award in IEC, the 1906 Award, for the development of standards, and in 2011, he received the ANS Walter Zinn Award, named after the first President of ANS and in 2017 was awarded the ANS Don Miller Instrumentation and Control Engineering Award, named after Dr. Don Miller from The Ohio State and in 2018 was recognized as a Fellow of the International Society of Automation (ISA).
Professor Yassin Hassan has been at Texas A&M University, College Station, since 1986. He is a professor in the Department of Nuclear Engineering and the Department of Mechanical Engineering. He received his Ph.D. and MS in nuclear engineering from University of Illinois, and MS in mechanical engineering from University of Virginia. Prior to his academic career, he was principal engineer (1980-1986) at Babcock & Wilcox Company's Nuclear Power Division in Virginia. Hassan has authored/co-authored over 100 refereed papers in various journals and several chapters in books. Hassan is a registered professional engineer in Texas and a Fellow of the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). He is also a member of several other societies, and chair of Nuclear Engineering of ASME. Hassan was the recipient of the George Westinghouse Gold Medal of ASME and Arthur Holly Compton Award of ANS. He has given invited lectures and short courses in the United States, Italy, Japan, Korea, Netherlands, Belgium and Mexico. Hassan's research interest is in the areas of computational and experimental fluid mechanics and turbulence, two-phase flow, laser-based flow visualization and diagnostic imaging techniques, and system modeling.