List of Invited Lecturers Under Finalization
see Panel Moderator
see also in plenary session order
Dr. David Aumiller has been employed at the Bettis Atomic Power Laboratory site of the Naval Nuclear Laboratory for more than 20 years as a thermal-hydraulic code and methods developer. He is a co-inventor of the R5EXEC software system which provides stable and well defined interfaces for reactor kinetics, T-H and control system coupling. He has published in the areas in the development of integrated code systems, numerically stable T-H coupling methods, uncertainty quantification, advanced verification techniques.
Plenary Lecture: Revisiting numerical techniques for sub-channel analysis codes
Dr. Maria Avramova is Associate Professor at North Carolina State University (NCSU). She serves as Director of the Consortium for Nuclear Power at NCSU, Director of Reactor Dynamics and Fuel Modeling Group, and Coordinator of the CTF Users’ Group. Avramova earned Ph.D. in nuclear engineering from the Pennsylvania State University. Between 1994 and 2001, she held a research scientist position at the Institute of Nuclear Research and Nuclear Energy, Bulgarian Academy of Science, Bulgaria. Avramova is a coordinator of the OECD LWR Uncertainty Analysis in Modeling Benchmark, and a member of OECD NEA Expert Group on Multi-Physics Experimental data, Benchmarking, and Validation.
Plenary Session: BEPU in Thermal-Hydraulics: Current issues, Challenges and Future Perspectives
Plenary Lecture: Uncertainty Quantification and Propagation in Core Thermal-hydraulics Sub-Channel Modeling and Simulation
Dr. Dominique Bestion is Research Director at CEA, professor at Ecole Polytechnique and teaches at INSTN, ECP, ENSE3. He has been developing two-phase flow models for the CATHARE system code for more than 30 years and coordinated modelling activities of the NEPTUNE multi-scale thermal hydraulic platform. He coordinated thermal hydraulic activities of the NURESIM, NURISP and NURESAFE European Projects for a reactor multi-physics and multi-scale simulation platform. He coordinates a Working Group of OECD-NEA for the application of CFD to nuclear safety. He is editor at the Nuclear Engineering and Design review. He is NURETH Fellow.
Dr. Milorad B. Dzodzo is a fellow engineer in Engineering Analysis Group in Westinghouse, Cranberry Township, Pennsylvania, USA. He obtained his Diploma in Engineering, M.Sc., and Ph.D. in 1977, 1983 and 1991, respectively from University of Belgrade, School of Mechanical Engineering, Serbia. Academic experience includes teaching and mentoring at three Universities: University of Belgrade, Serbia, 1979-1992, University of Akron, Ohio, USA, 1992-1996, and Carnegie Mellon, Pittsburgh, USA - fall 2011. Industry research experience started at Westinghouse Science and Technology Center, in Pittsburgh, Pennsylvania, USA, in 1996 and extends over twenty-four years including multiple CFD projects relevant to fuel assembly designs, and evaluation of other components in the plant like primary coolant pumps, primary moisture separators, pipe networks, etc. Leading scaling analysis to support designs of integral and separate effects test facilities for small modular reactor development. Support of AP1000 licensing related to containment atmosphere natural circulation and pressure response. Research expertise and interests include analysis, numerical modeling and experimental testing in a variety of fields such as: Heat Transfer, Nuclear Engineering, Scaling Analysis, Computational Fluid Dynamics, Flow Visualization, Tribology, Turbomachinery, Thermodynamics, Heating, Ventilation, Air Conditioning, and Solar Energy Conversion.
Plenary Session: BEPU Methodologies and V&V Process
Plenary Lecture: Scaling Issue and BEPU
Dr. Horst Glaeser got his PhD in Process Engineering in 1976 from Technical University Berlin, Germany. Afterwards, he worked in the design and construction of chemical plants and nuclear reprocessing plants at UHDE GmbH in Dortmund, Germany. He joined the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) in Garching close to Munich, Germany in 1980. Since 2002 he was Head of Cooling Systems Department at GRS up to his retirement in July 2014. He was lead manager of the development and application of the statistical GRS uncertainty analysis method. Now he is Senior Consultant in nuclear reactor safety analysis.
Plenary Session: BEPU Methodologies: Historical Remarks and Regulatory Requirements
Plenary Lecture: Historical Perspective of BEPU Methods
Dr. Jean-Marie Le Corre is a fellow engineer at Westinghouse in Västerås, Sweden. He has 20 years of experience working with LWR fuel thermal-hydraulics code development, testing and safety analysis. His main interests include the experimental investigation and physical modeling of high pressure convective boiling two-phase flow systems and associated uncertainties. He is also the lead thermal-hydraulic designer for the new Westinghouse TRITON11TM BWR fuel. Dr. Le Corre holds a M.S. degree in Nuclear Engineering from Purdue University and a Ph.D. degree in Mechanical Engineering from Carnegie Mellon University.
Plenary Lecture: Thermal-hydraulics BEPU Concepts for BWR Fuel Licensing & Safety Analysis
Dr. Robert Martin leads the development of evaluation methodologies for the design and safety analysis of advanced reactor concepts at BWX Technologies, Inc. Throughout his career in the nuclear industry, he has been responsible for the development and regulatory defense of several evaluation methodologies for the design and safety nuclear power plants, including the first licensing applications of best-estimate plus uncertainty methods to design-basis LOCA for both fuel and containment evaluations and for demonstrating plant resiliency to beyond design-basis severe accidents. Most recently, he led the team that produced the textbook “Design Basis Accident Analysis Methods for Light Water Reactor Nuclear Power Plants” (World Scientific, 2019).
Plenary Lecture: A Value Proposition for BEPU and Data-Analytics Methods to the Nuclear Industry
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.
Plenary Session: BEPU Methodologies: Historical Remarks and Regulatory Requirements
Plenary Lecture: Deterministic Safety Analysis for Nuclear Power Plants: IAEA Strategy and Approach
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.
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.
He is currently distinguished researcher, working for Korea Atomic Energy Research Institute (KAERI) since 1985. Previous positions in KAERI include former VP for nuclear safety research, former division director of thermal-hydraulics (TH) safety research, and general PM for TH research projects. He is also a Professor in charge of the major “Advanced Nuclear System Engineering” at Korean University of Science & Technology (UST) since 2008. He was adjunct research professor in UIUC, Illinois, USA (2017-2018) and visiting researcher in CEA-Grenoble research center, France (1987-1989). He is editor of Nuclear Engineering and Design (NED), and international advisory board member of Journal of Nuclear Science & Technology (JNST) and editorial board member of KernTechnik. He has been working, as bureau member, for OECD/NEA CSNI and WGAMA working group for several years. He is now serving as chair of thermal hydraulics division (THD) of American Nuclear Society (ANS). He served as chair and/or member of scientific/technical/organizing committee of various international conferences, and has been invited as lecturer in many international conferences, including IHTC, NURETH and NUTHOS. He has published over 110 papers in refereed journals and over 60 registered patents on thermal-hydraulics and nuclear safety. BS and MS in mechanical engineering and Ph.D. in nuclear engineering.
Plenary Session: BEPU Methodologies and V&V Process
Plenary Lecture: On the Scalability of Validation Data for BEPU Analysis
Mr. Gerhard Strydom is the National Technical Director for the United States Department of Energy’s (DOE) Advanced Reactor Technology (ART) Gas-Cooled Reactors (GCR) campaign. He is responsible for overseeing the $30M/year TRISO fuel and graphite qualification programs at Idaho National Laboratory (INL), in addition to the ART GCR program activities on high-temperature alloys and High Temperature Gas-Cooled Reactor (HTGR) simulation method development and validation activities. He represents the US DOE on the IAEA HTGR Technical Working Group (TWG) and served as US member of the Generation-IV Forum VHTR System Steering Committee and Expert Group since 2016. His primary technical focus areas are coupled neutronics and thermal fluid HTGR analysis and uncertainty propagation from lattice to transient simulations. Recent work includes leading the prismatic HTGR benchmark for the IAEA Coordinated Research Program (CRP) on HTGR uncertainties and the coupled steady state and transient exercises of the OECD/NEA transient benchmark on the 350 MW prismatic Modular High Temperature Reactor. Prior to joining INL in 2010, Mr. Strydom worked at the Pebble Bed Modular Reactor (PBMR) company for 7 years, where he led the PBMR core design and accident analysis team for 2 years in the role as the primary safety case transient analysist. He is the author of more than 30 journal and conference publications and will receive his Ph.D. on the development of a multi-phase and multi-physics uncertainty assessment methodology for prismatic HTGRs in September 2020.
Plenary Session: BEPU Methods and Results for GEN-IV & Other New Designs
Plenary Lecture: Uncertainty analysis and modeling for HTGR