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KIVANOV Kostadin Ivanov

President, Founder

 CV

  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.

         

Petruzzi  Alessandro Petruzzi

   Founder

  CV 

 

 Alessandro Petruzzi is the President of NINE and current Head of the Plant Thermal-Hydraulics Area devoted to safety analysis and licensing of NPP. Prior to join NINE, he worked over 9 years in the Nuclear Research Group of San Piero a Grado (GRNSPG) and he spent the year 2004 working as an intern-assistant in the Pennsylvania State University (USA). He got his PhD Degree in “Nuclear and Industrial Safety” Course of the “Leonardo da Vinci” Doctoral Engineering School in 2008, discussing the thesis titled “Development and Application of Methodologies for Sensitivity Analysis and Uncertainty Evaluation of the Results of the Best Estimate System Codes applied in Nuclear Technology”. The methods for uncertainty and sensitivity analysis applied to thermal-hydraulics system codes constitute his main interest as well as the assessment of computer codes and the development of sensitivity and uncertainty methods. He is the founder and director of the seminar-courses 3D S.UN.COP (Scaling, Uncertainty and 3D COuPled Code Calculation), the NRSHOT (Nuclear Reactor Safety Hand-On Training) and MMARS (Models and Methods for Advanced Reactor Safety Analysis) which have been organized several times all around the world.

             

Avramova  Maria Avramova

   Vice-President,Founder

  CV

 

  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.

         

Modro  S. Michael Modro

   Founder

  CV

 

  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).

             

Popov Nikola Popov

Founder

CV

 

 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.

         

Quinn Edward L. Quinn

Founder

CV

 

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). He currently serves on the Board of five companies and two university advisory boards and is the retired Chair of The Ohio State Nuclear Engineering Advisory Board. Mr. Quinn hold a B.S. in Electrical Engineering from Tufts University, Medford, MA, and a Masters in Management from Rensselaer Polytechnic Institute in Troy, N.Y. and was a Naval Nuclear Qualified Shift Test Engineer (NAVSEA 08), Jan, 1977.

             

Kristof  Marián Kristof

   Founder

  CV

 

 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.

         

Cherubini  Marco Cherubini

   Founder

  CV

 

 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. Along his carrier he worked on the safety assessment of different reactor types including PHWR , VVER and RBMK. 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. Since 2013 Nuclear fuel behavior became his first priority topic of interest, though continuing its involvement in thermal hydraulics activities. He is taking part at different International OECD-NEA and IAEA initiatives including code benchmarking, noticeably in nuclear fuel simulation, and contribution to several CSNI publications. Scientific activities include authorship of papers published in international journals and presented in several conferences.

Marquino  Wayne Marquino

          Managing Director

          CV

 

 Mechanical engineer with knowledge and skills in nuclear power safety and performance analysis, regulatory compliance and license amendments, heat transfer, fluid flow, simulation, I&C, normal and accident radiation dose.