The number of invited lecturers is determined on the basis of the registrations received (about 10 lecturers if the registrations are less than 10; all lecturers if the registrations are more than 20).

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.

 Giovanni Bruna is a Dr. in Nuclear Physics and he has more than 40 years of experience in reactor safety, design and operation. He is the scientific director IRSN - French Institute for Radioprotection and Nuclear Safety. Previously, he was IRSN’s Deputy Director for reactor safety, and AREVA group’s manager nuclear reactor physics & senior international expert.

Dr. Marco Cherubini is the Vice-President of NINE and current Head of the Core Behavior Area devoted to prediction and analysis of NPP core by different disciplines viewpoint. Prior to join NINE, he worked over 7 years in the Nuclear Research Group of San Piero a Grado (GRNSPG) being responsible for System Thermal-Hydraulics simulations. He got his PhD Degree in “Nuclear and Industrial Safety” Course of the “Leonardo da Vinci” Doctoral Engineering School in 2008, discussing a thesis dealing with Accident Management in VVER-1000. In the last three years Nuclear fuel behavior became his first priority topic of interest, continuing its involvement in thermal hydraulics activities. He is taking part at different International OECD-NEA and IAEA activities including code benchmarking, noticeably for the nuclear fuel.

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 two years. 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.

Professor Mamdouh El-Shanawany is an international expert on nuclear safety. For the last 40 years, he has provided leadership, design, research & development, analysis, management and critical safety assessment, applications of Statutory regulatory requirements and policy development for the nuclear industry in the UK, Canada and Internationally. He was a member of the IAEA team which was awarded the Nobel Prize for Peace in 2005. He was global Nuclear Technical Director at Lloyd's Register, and visiting Professor of Nuclear Safety Centre for Nuclear Engineering, at the Imperial College, London University. Dr El-Shanawany was the Head of the Safety Assessment Section at the IAEA, The main responsibilities of the Safety Assessment Section are to strengthen Member States’ capabilities (Regulatory Bodies, Designers and Operators) in effective safety assessment and safety enhancement of nuclear installations. He represented the IAEA on the Commission of Nuclear Safety Standards, International Nuclear Safety Group. Also, he represents the IAEA at the OECD/ Nuclear Energy Agency, CSNI and the Technical Steering Committee of the Multinational Design Evaluation Programme. Dr El-Shanawany is an Independent Expert Evaluator for research project allocations, UK Engineering & Physics Science Research Council and Euratom Nuclear Research and Training, European Commission. He was also a member of Generation IV Technical Advisory Committee of the UK Government's Department of Trade and Industry. El-Shanawany is also an excellent communicator and mentor, able to understand issues in a multi-dimensional environment, providing solutions that support various stakeholders. Prior to joining the IAEA, he was employed by Her Majesty’s Nuclear Installations Inspectorate, the UK Regulatory Body, where he was responsible for managing, assessing and formally agreeing and accepting the Licensees’ arrangements and safety cases for faults studies and severe accidents analysis for the operating plants. He holds a PhD in Thermal Power Section from the Imperial College of Science and Technology (London).

Dr. Cesare Frepoli (PhD, 2001, Penn State; ME, 1990, Politecnico di Milano, Italy) is the founder and CEO of FPoliSolutions, LLC. The firm specializes in developing software solutions in the energy sector. Dr. Frepoli has 27 years’ experience in the nuclear industry. Areas of expertise include numerical modelling and simulation of fluid systems, thermal-hydraulic processes and data analysis for computer codes development and validation. Dr. Frepoli is the inventor and developer of important uncertainty analysis methodologies currently used in the industry (Westinghouse Electric Company ASTRUM and full Spectrum LOCA). Dr. Frepoli acquired a vast knowledge in legacy thermal-hydraulic test programs and participated in several key experimental campaigns in support to the licensing nuclear power plants. 

Dr. Walter Giannotti has PhD graduated in Nuclear Engineering at Pisa University. He is a senior nuclear engineering of the Nuclear and Industrial Engineering srl (NINE). He has more than twenty years of experience working in the system thermal-hydraulics safety analysis. He performed code applications for safety analysis o PWR, BWR, VVER and PHWR nuclear power plant related to thermal-hydraulic and severe accident analysis. He worked on Code Assessment (Relap, Cathare, Melcor, Smart) and Best Estimate Plus Uncertainty Methods (UMAE). From 1996 to 2012 he was a consultant of University of Pisa in the EU Tacis Project devoted to Deterministic safety analysis for VVER, RBMK and the preparation of the Chapter 15 of FSAR for the Argentinean NPP Atucha-2, SA analysis (Melcor, SCDAP, Gothic codes) of WWER (Temelin, Kozloduy), RBMK (Ignalina), PWR (Angra), PHWR (Atucha). He was senior expert in ”European Project for Technical Assistance for Implementing Nuclear Safety Project - Thermo-hydraulic experiments at the PSB-RBMK integral Test facility”. He performed, as tutor, courses concerning Nuclear Safety for VATESI-Lithuania (spent fuel), CNEN-Brasil (severe accident), CNPE-China (severe accident), ANRA-Armenia (safety analysis).  From 2013 is a consultant of IAEA for supporting the development of nuclear competences in severe accident. He is in the Task Group WGAMA - OECD for “Long-term management guide” and “Informing SAM guidance and actions”. In 2012 he worked as nuclear expert in the ”Final Design for the EUREX plant in Saluggia of the Waste Management Facility (WMF)”. He is qualified radioprotection expert (first level) and he is involved in radioprotection field (shielding and safety analysis) in nuclear and conventional environment.

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.

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.

Dr. Marián Krištof, CEO of the Network of Nuclear Engineering and Energy Services (NNEES), manages the international network of senior experts in the area of nuclear safety assessment and licensing to support various organizations ranging from regulatory authorities, TSOs and research institutes to nuclear power plant operators. He is international consultant specializing on diverse aspects of nuclear safety including TH safety calculations, uncertainty analysis, preparation and/or review of the safety related documentation, preparation of trainings and lectures and management of domestic and international projects in the area of nuclear safety. For several years he is assisting the IAEA in development and implementation of its SAET (Safety Assessment Education and Training) program. The objective of the program is to support the embarking countries in their safety assessment competence building. He worked over a decade for the Slovak regulator as an analyst performing independent safety assessment of the NPPs including code calculations, prepared and reviewed the regulatory documents such as acts, regulations or safety guides and reviewed of the safety related technical documentation to support the regulatory decision-making.

Dr. Robert Martin (Nuc Eng Phd 1996, Penn State; Nuc Eng BS ‘87, MS ‘89, Texas A&M) is a Technical Consultant at BWX Technologies leading the safety analysis methods team for the mPower™ small modular reactor program.  He has over twenty-five years of professional experience in the development and regulatory defense of nuclear-thermal-hydraulic evaluation methodologies for both design-basis coolant system faults and severe accidents.  The development of these methods has been through industry- and DOE-sponsored programs advancing conventional LWRs, the SRS production reactors, AP600, SBWR, PIUS, USEPR, VHTR (gas), mPower and the TWR-P (sodium) designs.  His experience includes employment at the Idaho National Laboratory supporting development of the RELAP5-3D thermal-hydraulic systems computer code.  He is also a long-standing member of the American Nuclear Society (ANS), serving on executive committees for both the Thermal-Hydraulic Division and the Nuclear Installation and Safety Division.

Dr. Jozef Misak has 47 years of experience in nuclear engineering/nuclear safety, mainly devoted to development and application of safety assessment tools applicable in design and operation of NPPs, broad experience in development of IAEA Safety Standards and other publications. More than 30 years of managerial experience in non-governmental, governmental and international organisations in various posts up to general director of the Nuclear Power Plant Research Institute in Slovakia, and first chairman of the Nuclear Regulatory Authority of the Slovak Republic, 1993-1997. During the period 1998-2004 Head of the IAEA Safety Development Unit. Extensively involved in safety missions and training activities organized by IAEA. Since 2005 he is working in UJV Rez (Nuclear Research Institute) as Vice-President for Strategy Development focusing mainly on management and coordination of nuclear safety matters in connection with major projects of the institute nationally and internationally. He published numerous research reports, scientific articles and presentations in the area of nuclear safety.

Dr.  Rafael Mendizábal obtained his Master of Chemistry and his Master of Physics from the Universidad Autónoma de Madrid and his Master of Mathematics from the Universidad Nacional de Educación a Distancia. He obtained a PhD in Science from the Universidad Politécnica de Madrid. He works since 1986 at the Consejo de Seguridad Nuclear in Spain. His areas of expertise are: Deterministic Safety Analysis on Nuclear Power Plants, Thermohydraulic Modelling and Simulation, Nuclear Fuel design analysis, Uncertainty and Sensitivity analysis.

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).

Dr. Mathew Panicker is a Reactor Engineer at the Nuclear Performance and Code Review Branch at the Office of Nuclear Reactor Regulation (NRR) of US NRC with technical lead for fuel design/performance methodology, core physics and core thermal hydraulics. Prior to NRC assignment, he was a nuclear design engineer at Fort Calhoun Nuclear plant (FCS) in Omaha, Nebraska. At FCS he performed core and thermal-hydraulic design and support for plant operation. He taught engineering courses at Southern Company NPPs.  He holds a Ph.D. and MS in Nuclear Engineering, MS and BS in Physics. Dr. Panicker is a licensed professional engineer (PE).  He was chosen as the Federal Engineer of the Year for the USNRC by National Society of Professional Engineers (NSPE) for 2018.

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.

Professor Nikola Popov has over 38 years of experience in the Nuclear sector in Canada and internationally. His field of work includes Thermal-Hydraulics, Safety Analysis, Licensing, Computer Codes Development and Validation and Severe Accident analysis. He is Adjunct Professor at McMaster University for the UNENE program (reactor thermal-hydraulics design and reactor thermal-hydraulics analysis) and also an Adjunct Professor at the University Cyril and Methodius- Faculty of Electrical Engineering, in Macedonia. He worked 23 years at the Atomic Energy of Canada (1988-2011), the last 3 years as the Director for Safety and Licensing. He also worked at SNC-Lavalin-Nuclear as Director of Safety and Licensing (2011-2014). He provides nuclear engineering consulting and educational services to several important institutions, including Ontario Power Generation, Canadian Nuclear Safety Commission, CANDU Owners Group, etc. Dr. Popov was involved and managed various projects at AECL, such as the licensing of advanced CANDU reactor in Canada, USA, UK, and other countries. He has a PhD in Mechanical Engineering at the University of Zagreb, Croatia.  

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).

Dr. Juswald Vedovi is the engineering manager of the Stability and Radiological Analysis team part of the Nuclear Analysis Center of Excellence at General Electric Hitachi (GEH) Nuclear Energy headquarters located in Wilmington, North Carolina (USA). In his role he is responsible for the technical areas of plants thermal-hydraulic stability analyses, plants noise analyses, PRNM stability support, radiological analyses, decay heat, spent fuel pool criticality, control blade analyses, fluence analyses and dose consequences.  He has 15 years experience in the area of safety analysis for PWR, BWR, ESBWR, ABWR, VVER reactors, simulation and analyses of transients like LB-LOCA, SB-LOCA, MSLB, ATWS, Turbine Trip, LOFWH, RIA, etc., using codes such as TRACG, TRACE, RELAP5, PANAC, PARCS, and ODYSY.  He also has extensive expertise in APRM/OPRM software/hardware system and plant noise analyses as part of the PRNM projects. He contributed to the ESBWR DCD and the Transient and Stability TRACG LTRs for ESBWR. He was the main author on four Licensing Topical Reports on thermal-hydraulics stability methodologies for BRWs submitted to the NRC, three of them already approved. He has supported safety analysis for several EPU, MELLLA+ and PRNM license amendments requests for operating BWRs. Dr. Vedovi has a Master of Science in Nuclear Engineering from Penn State Univeristy (USA) and a Ph.D. in Nuclear Engineering from Univerisity of Pisa (Italy). Dr. Vedovi is also a 2011 graduated fellow from the World Nuclear Univeristy attended in Oxford, UK. Dr. Vedovi currently serves as a member on the Nuclear Power Advisory Board of Penn State University (USA).