International Conference
on Nuclear Engineering®

Novotel London West, London, England

July 22 - 26, 2018

July 23 - 26, 2018



Panel Sessions


Panel Title: Leak Before Break (LbB) and Leakage Through Cracks

Panel No: 1
Date & Time: Monday, July 23, 2018 @ 2 PM
Meeting Room: Cremant Room
Panel Organizer/Leader: Jovica Riznic


  1. Peter Gill, Consultant
  2. John Sharples, Wood PLC
  3. Gary Wilkowski, MC2
  4. Klaus Heckman, GRS
  5. Jinya Katsuyama, JAEA
  6. David Rudland, USNRC

Focus: Feedback on construction management, construction technology, and construction challenges.

Abstract:  Leak-before-Break (LbB) is a structural integrity assessment methodology which provides a means of justifying safe operation of Nuclear components through the concept of large break preclusion.  This can be achieved through the application of fracture mechanics to determine limiting defect sizes and crack opening areas, along with fluid mechanics to determine leakage rates.  LbB has been successfully applied in many different countries to meet the relevant regulatory requirements.  The objectives of this expert panel session are as follows:

  • Introduce the fundamental concepts of LbB
  • Highlight the latest research in this topic
  • How the regulatory environment shapes the requirements of LbB procedures


John Sharples

John Sharples is a Technical Manager and Chief Technologist in the field of structural integrity at Wood. He has worked in the nuclear industry for over 30 years, mainly on developing, validating and applying structural integrity assessment procedures. A large part of his work has been associated with the R6 fracture mechanics procedures, the BS7910 fitness-for-purpose code and numerous European projects, including STYLE+ and the NULIFE Network of Excellence, focused on plant life management and plant life extension issues. John sits on the NUGENIA Executive Committee.

Dr Peter Gill

Dr Peter Gill is a Chartered Mechanical Engineer, specializing for the last 8 years in Structural Integrity within the Materials Science and Structural Integrity (MSSI) business of Wood. Peter works on plant assessment methodologies, and performs research and development on Leak-before-Break and environmental fatigue. He completed a Nuclear Engineering doctorate entitled “Investigating leak rates for Leak-before-Break assessments” at the University in Manchester in 2013. Since then he has had a lead role in developing the Leak-before-Break section of the R6 structural integrity assessment procedure. Peter has also developed sessions at the ASME Pressure Vessels and Piping conference and is a visiting researcher at the Dalton Nuclear Institute at the University of Manchester.

Dr. Gery Wilkowski

Dr. Gery Wilkowski has been involved in conducting experimental and analytical pipe fracture mechanics projects since 1974. He received his bachelor’s and master’s degrees in mechanical engineering from University of Michigan and his PhD in Nuclear Engineering from University of Tokyo. He has published over 400 papers on oil and gas pipelines, as well as nuclear pressure vessels and piping systems and fracture toughness testing. He was involved with the technical basis of the original NRC Draft Standard Review Plan 3.6.3 on LBB, and conducted large project on piping fracture behavior for the NRC and the International Piping Integrity Research Group Program (IPIRG). He has been a technical editor of several journals, and is an ASME Fellow since 1997. He was the Chairman or Vice-Chairman of the ASME PVP Division’s Materials and Fabrication Committee for 8 years, has been a member of the ASME B&PV Code Section XI Committee since the early 1980’s, and is the current secretary of the Section XI Working Group on Pipe Flaw Evaluation since about 1990. He founded Engineering Mechanics Corporation of Columbus in 1998 after being at Battelle-Columbus for 23 years. He has developed the Lie-Balanced Putter System that is USGA/R&A approved, patented, and went into commercial production in 2016. He enjoys golf, drinking beer, eating fresh oysters, and drinking beer

David Rudland

David Rudland is a Senior Technical Advisor for Nuclear Materials in the Office of Nuclear Reactor Regulations at the U.S. Nuclear Regulatory Commission where he has worked for ten years. He is the Division of Materials and License Renewal subject matter expert in the area of nuclear materials and component integrity with an emphasis on probabilistic fracture mechanics, solid mechanics and materials aging management. He is also the NRC representative on the ASME Board of Nuclear Codes and Standards and heavily involved in both the ASME Section XI code committees and the ASME PVP Division. Before joining the NRC, he worked as an NRC contractor at Engineering Mechanics Corporation of Columbus and Battelle Memorial Institute. Dr. Rudland received a Bachelor’s and Master’s degree in Mechanical Engineering from the University of Illinois, and a Ph.D. in Materials Engineering from Yokohama University in Japan through a visiting scholar program.

Dr. Jinya Katsuyama

Dr. Jinya Katsuyama is a Principal Researcher in Nuclear Safety Research Center of Japan Atomic Energy Agency (JAEA). In 2004, he started to research on the structural integrity assessment method based on weld residual stress analysis at Osaka University. From 2006, he has been engaged in research on the aged degradation of nuclear components such as neutron irradiation embrittlement in reactor pressure vessel, stress corrosion cracking and fatigue in piping welds at JAEA. In addition, he has been developing deterministic and probabilistic fracture mechanics methodologies for reactor pressure vessel and primary piping in light water reactors. Currently, he contributes to development of a guideline on probabilistic fracture mechanics analysis methodology focusing on its practical use in Japan.

Dr. Klaus Heckmann

Dr. Klaus Heckmann, studied physics in Darmstadt (Germany) and Grenoble (France). He earned his PhD in Nuclear Physics in 2011. Since 2012 he works for Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH in Cologne/Germany, in the structural mechanics group. His professional interest is focus on Leakage rates, fracture mechanics, probabilistic methods and techniques, and software development.

Panel Title: Experience Feedback of New Nuclear Power Plant Construction

Panel No: 2
Date & Time: Tuesday, July 24, 2018 @ 2 PM
Meeting Room: Cremant Room
Panel Organizer/Leader: Zhi Wang (Chinese Nuclear Society), Hideo Soneda (Hitachi)


  1. Fengwei Song, China Zhongyuan Engineering Corporation
  2. Jiang Tai, CNPE
  3. Yusuke Amma, Hitachi-GE Nuclear Energy
  4. Cuifang Wang, SNERDI
  5. Donghai Wang,CNPE

Focus: Feedback on construction management, construction technology, and construction challenges.


Fengwei Song

Mr. Fengwei Song is Vice President of China Zhongyuan Engineering Corporation, a subsidiary of China National Nuclear Corporation. He is also working as General Manager of Karachi Nuclear Power Project Unit 2& Unit 3 in Pakistan. Mr. Song received a bachelor’s degree in welding processing from Jiangsu University of Science and Technology in 1985. He has been working at the frontier of nuclear power projects for over 30 years and contributed to many nuclear power projects in China such as Qinshan NPP, Daya Bay NPP, Haiyang NPP, Tianwan NPP. He has worked as general manager for five different nuclear power projects and is well known for his expertise in M310, VVER, AP1000 and HPR1000 as well as his safety management methodology and produced innovative construction methods. He is the sole author of Pre-introduction of HPR1000 Primary Loop Equipmentand first author of Research on Chemical Treatment of Marine Organism for Coastal Nuclear Power Plant as sole author and Modular Construction of Reactor Pit Pool for a Nuclear Power Plant and Application of MVC on a Nuclear Power Plant Seawater Desalination Design.

Tai Jiang is deputy chief engineer of CHINA NUCLEAR ENGINEERING Co., LTD (CNPE), he is also chief engineer of FUQING NUCLEAR POWER PROJECT Department of CNPE. Tai JIANG had worked at BEIJING INSTITUTE OF NUCLEAR ENGINERING as material engineer for 17 years from 1987 to 2004.Tai JIANG had taken part in LINGAO NUCLEAR POWER PROJECT PHASE 2 ,FUQING NUCLEAR POWER PROJECT PHASE 1 and FANGJIASHAN NUCLEAR POWER PROJECT as manager of design department from 2005 to 2013. From 2013 to present, Tai JIANG has worked FUQING NUCLEAR POWER PROJECT Department of CNPE , which is in charge of management FUQING UNIT 5&6, FUQING UNIT 5 is first unit of HTR1000.

Yusuke Amma is the Construction engineer of Nuclear Plant Department of Hitachi-GE Nuclear Energy, LTD. He had started to work as a welding engineer in Nuclear Manufacturing Department. He had worked at Shimane Nuclear Power Plant Construction Project for 3 years as installation supervisor from 2008 to 2011. After that he had also take part in Fukushima nuclear power plant as a supervisor after Fukushima disaster. From 2012 to present, he have worked at Wylfa Newydd nuclear power station project as a construction planning team.

Cuifang Wang

Mrs. Cuifang Wang is the Deputy Director of Project Management Dept. of Shanghai Nuclear Engineering Research & Design Institute(SNERDI), and is the deputy Project Manager of CAP1000 standard design project and Sanmen Phase-2 design project. She has 15 years experience of I&C system design and 8 years of project management experience for the nuclear power plants. Beginning from 2010, Mrs. Cuifang WANG contributed herself on the development and operation of experience feedback system in SNERDI. Her team built the procedures and software platform, established relations with owners, engineering company, manufacturers to collect experience feedback to optimize the design of CAP project.

Donghai Wang

Donghai Wang is the director of quality assurance department of CNPE (CHINA NUCLEAR POWER ENGINEERING CO., LTD). He has worked in BINE and CNPE for 25 years (BINE-Beijing Institute of Nuclear Engineering). From 1993 to 2015, he was responsible for the design of ultimate heat sink, water intake and discharge, water supply and drainage, fire fighting, water treatment, cooling tower for nuclear power plants. Since 2016, he takes in charge of quality assurance of CNPE. Donghai Wang received a Bachelor’s degree in Water Treatment from Wuhan University, and a Master’s degree in Nuclear Energy Science and Engineering from Harbin Engineering University.

Panel Title: Robust Fuel Development

Panel No: 3
Date & Time: Tuesday, July 24, 2018 @ 2 PM
Meeting Room: Bouzy Room
Panel Organizer/Leader: Sumit Ray (Westinghouse), Hisaki Sato (Toshiba), Min Xiao (CGN)


  1. Sumit Ray, Westinghouse
  2. Gwen Bolsee, Areva
  3. Min Xiao, CGN
  4. Hisaki Sato, Toshiba Energy Systems & Solutions Corporation
  5. University of Tennessee

Focus: Fuel reliability, fuel material, and fuel fabrication.


Min Xiao

Min Xiao,     Ph.D,  Professor,  Deputy Chief  Engineer
China Nuclear Power Research Institute (CNPRI)/China General Nuclear Power(CGN)
Great contribution in the field of reactor core design, fuel management and PWR fuel industry in China. Organize and implement a series of advanced core design and fuel management projects for China 1000MWe




PWRs including:

  • Daya Bay NPP 18 Month Fuel Cycle, first in China
  • Severe Accident Management Guideline Implementation in Daya Bay NPP, first in China,
  • Ling Ao Advanced Fuel Management (1/4 refueling) project. First in China
  • PWR Initial Core 18 Month Project with Gadolinia-bearing Fuel. First in the world.

Awards including:

  • First prize of National Defense Science and Technology.
  • First prize of China National Nuclear Industry Science and Technology Achievements.
  • Grand ICONE AWARD ( ICONE25,  in Shanghai, China, 2017

Academic Activities

  • Vice-Chairman of Shenzhen Science-Technology Expert Association.
  • Expert of International cooperation experts group of the China Atomic Energy Agency(CAEA). Contact Expert of China-Euratom Nuclear Cooperation on Nuclear Reactor Safety for Euratom Working Programme 2018 in Horizon 2020
  • Track 2 Chair of ICONE25.  
Hisaki Sato

Hisaki Sato is a group manager of Nuclear Core & Fuel group in Nuclear Safety System Design & Engineering Department at Toshiba Energy Systems & Solutions Corporation. He has 17 years experience in nuclear industry, 10 years in Nuclear Core & Fuel group and 7 years in Nuclear Safety System group. In 2001, He joined Toshiba to work for neutronics and thermal-hydraulics engineering of Nuclear Core & Fuel. After Fukushima Daiichi NPPs accident, He engaged in work of R&Ds for nuclear safety enhancement technologies for several years. Since 2016, He has been in charge of an Accident Tolerant Fuel development project of Toshiba.

Panel Title: Intelligent Technology Applications in Nuclear Power Plants

Panel No: 4
Date & Time: Wednesday, July 25, 2018 @ 2 PM
Meeting Room: Chalon Room
Panel Organizer/Leader: CNS, Ken Canavan (Westinghouse)


  1. CNS
  2. Ken Canavan, Westinghouse

Focus: Smart equipment, smart detection, control, and prognostic data mining to improve the performance and safety level of NPPs.


Panel Title: Education and Human Resources Development

Panel No: 5
Date & Time: Wednesday, July 25, 2018 @ 2 PM
Meeting Room: Chalon Room
Panel Organizer/Leader: Asif Arastu, Yassin Hassan, Leon Cizelj, John Roberts, Hiroshige Kikura, Kan Wang


  1. Yassin Hassan, Texas A&M
  2. Guanghui Su, Xi’an Jiaotong University
  3. Leon Cizelj, Josef Stefan Institute
  4. Akihide Kugo, JANSI
  5. Kan Wang, Tsinghua University
  6. Hiroshige Kikura Tokyo Institute of Technology

Focus: Issues related to the best practice of public acceptance, education, and human resources development.


Yassin Hassan

Yassin Hassan is Professor and Head of the Department of Nuclear Engineering, Sallie and Don Davis’61 Professor of Engineering and also Professor of the Department of Mechanical Engineering at Texas A&M University. Prior to joining Texas A&M September 1986, he worked for seven years at Nuclear Power Division, Babcock & Wilcox Company, Lynchburg, Virginia. His research is in computational and experimental thermal hydraulics, reactor safety, laser-based flow visualization and diagnostic imaging techniques, system modeling, multiphase flow, transient and accident analyses and advanced nuclear reactors.

Guanghui Su

Guanghui Su is a professor of Xi’an Jiaotong University, and he is the winner of the National Science Foundation for Distinguished Young Scholars of China, Yangtze river scholars Distinguished Professor. He is the co-editor of ASME Journal of Nuclear Engineering and radiation Science and as TPC Chair of ICONE18 held in Xi'an,2010.

Leon Cizelj

Leon Cizelj is the Head of Reactor Engineering Division of the Jožef Stefan Institute, Ljubljana, Slovenia (http://r4.ijs.si/en). Responsible for the strategic and operational leadership of the division active in the field of nuclear engineering and safety of nuclear installations. Activities include research, postgraduate education, technical and scientific support to the Slovenian nuclear regulatory body and technical and scientific consulting to end users. Full professor of nuclear engineering at the University of Ljubljana, Slovenia, Faculty of mathematics and physics. President of the ENEN (European Nuclear Education Network www.enen.eu) Association in 2016, 2017 and 2018.Associate editor of Journal of Nuclear Engineering and radiation Science ASME. Member of the editorial board of Science and Technology of Nuclear Installations. Ph. D. in Physics 1993, University of Ljubljana, Slovenia. Author or coauthor of more than 690 publications more than 100 interviews in the Slovenian mainstream media.

Dr. Akihide Kugo

Dr. Akihide Kugo is Executive Officer and General Manager for International Department of Japan Nuclear Safety Institute. Dr. Kugo dedicated himself in developing leadership educational programs for nuclear operators such as from the CEOs to the first-line managers. Dr. Kugo is also a member of Working Group on Human and Organizational Factors (WGHOF) of CSNI OECD/NEA. From the aspects of human attributes, Dr. Kugo established the program of a crisis management drill and exercise based on the episodic memories of Fukushima Accident. He also applied the methodology of psychological model of Johari-Window to the assessment of leadership training for shift supervisors of nuclear power station. Dr. Kugo received a bachelor’s degree in Mechanical Engineering from Tokyo University in Japan, and Master degree of Arts in International Study from Leeds University in U.K., and Ph.D. in Energy Science from Kyoto University in Japan. Dr. Kugo currently looks after the international business of JANSI.

Kan Wang, PhD, Professor of Nuclear Engineering and Director of Institute of Nuclear Energy Science and Engineering Management (INESEM) at Department of Engineering Physics in Tsinghua University, Beijing. Main research interests include: Development of nuclear numerical reactors, Monte Carlo methods and multi-physics coupling applied in reactor analysis, New and advanced thorium-based nuclear energy system, Safety analysis. About 680 journal and conference papers have been published, 35 PhD have been fostered while 20 PhD students are at study. Consulting work include: China Nuclear Power Society (Vice President), China Nuclear Education Society (Vice President), Beijing Nuclear Society (Vice President), Academic Committee of Reactor Design Technology Key Lab (Vice Director), etc.

Panel Title: Fukushima-Daiichi Nuclear Power Plant Decommissioning R&D

Panel No: 6
Date & Time: Tuesday, July 24, 2018 @ 2 PM
Meeting Room: Reims Room
Panel Organizer/Leader: Yasuo Koizumi (JAEA)


  1. Kazuhito Takeda, TEPCO, “Current Status and Challenges at Fukushima Daiichi Decontamination and Decommissioning”
  2. Hideo Soneda, Hitachi-GE Nuclear Energy
  3. Koji Okamoto, JAEA, CLADS
  4. Hiroshige Kikura, Tokyo Institute of Technology
  5. Claire Corkhill, University of Sheffield

Focus: The current status, lessons learned, and actions of post Fukushima Daiichi accident.

Panel Title: Communication with Nuclear Stakeholders

Panel No: 7
Date & Time: Tuesday, July 25, 2018 @ 2 PM
Meeting Room: Cremant Room
Panel Organizer/Leader: Leon Cizelj, Hiroyuki Yamada (CRIEPI)


  1. Hiroyuki Yamada, CRIEPI
  2. Leon Cizelj, Josef Stefan Institute
  3. Kristy Gogan, Energy for Humanity
  4. Asif Arastu, Unisont Engineering, Inc
  5. Nathon Paterson, Rolls-Royce

Abstract: Why would nuclear professionals need communication skills? We may start with the fact that nuclear professionals communicate a lot in their daily work. This is communication between peers, is part of the training and is superbly mastered by most of the professionals. Then, in the everyday life, better communication skills could lead to better and more satisfying relations with the people that we interact with. Finally, the nuclear professionals could further develop their already considerable communication skills to communicate about the nuclear technologies beyond their peers. The workshop will provide the insight in the basic communication techniques and traps that might then be used by the participants in the real-life situation.


Dr. Hiroyuki Yamada

Dr. Hiroyuki Yamada is a Senior Research Scientist in Nuclear Risk Research Center of Central Research Institute of Electric power Industry (CRIEPI). He has been engaged in nuclear safety research on the seismic PRA since 1996 in Japan Atomic Energy Research Institute (JAERI). In 2002, he started to research on the disaster mitigation and communication based on the spatial temporal information system in National Research Institute for Earth Science and Disaster Prevention (NIED). From 2007, he has been engaged in research on the nuclear risk communication in Japan Nuclear Energy Safety Organization (JNES). He was involved in IAEA project of Tsunami EBP from 2007 to 2010. He has developed TiPEEZ (Tsunami and Post Earthquake Response in the External Zone) system, and TiPEEZ system for disaster management was implemented in Member States. From 2014, he has been engaged in research on risk communication and seismic/tsunami PRA in order to assist nuclear operators and nuclear industry to continually improve the safety of nuclear facilities. He is a Specially Appointed Professor in Graduate School of Engineering of Niigata Institute of Technology since 2016.

Panel Title: Advanced Manufacturing

Panel No: 8
Date & Time: Wednesday, July 25, 2018 @ 2 PM
Meeting Room: Bouzy Room
Panel Organizer/Leader:  Craig Stover (Chair), Tomofumi Yamammoto (Co-Chair)


  1. Craig Stover – EPRI (Chair) Opening Remarks
  2. Tomofumi Yamamoto – MHI (Co-Chair) Opening Remarks
  3. Dr. Michael Preuss – The University of Manchester
  4. Dr. Will Kyffin – Nuclear Advanced Manufacturing Research Centre
  5. Eleonora Lambis – Westinghouse
  6. Naoki Suda – MHI

Focus: The use of advanced manufacturing techniques in nuclear-related applications


Eleonora Lambridis

Eleonora Lambridis is the manager of Westinghouse’s global open innovation program WeLink. In her role, she has the mission to explore and develop new technologies to the nuclear industry through collaboration with startups, small and medium sized enterprises (SMEs), and research centers. Eleonora has been an innovation leader for Europe Engineering for the past 3 years, and since 2010 has worked as an engineer and project manager for Westinghouse in various roles of increasing responsibility. She has an M.B.A. degree from the Solvay Brussels School of Management and Economics (Belgium) and a master degree in nuclear engineering from the University of Rome La Sapienza (Italy).

Naoki Suda

Naoki Suda is a research engineer of MHI (Mitsubishi Heavy Industries, LTD.). He performs research and development of welding technology. He has developed welding sensing and automatic welding technology. He was a manufacturing and welding engineer about nuclear power plant equipment before he became current job position. He obtains international welding engineer, IWE.

Panel Title: SMRs & Advanced Technologies

Panel No: 9
Date & Time: Wednesday, July 25, 2018 @ 2 PM
Meeting Room: Epernay Room
Panel Organizer/Leader:  Bob Stakenborghs, Tian Lin (SNERDI), and Kohei Hisamohi (Hitachi)


  1. NuScale 7. Kazuaki Kito, Hitachi-GE Nuclear Energy
  2. Rolls-Royce
  3. Xujia Wang, SNERDI
  4. Yu Liu, NPIC
  5. Paolo Ferroni, Westinghouse
  6. KAERI
  7. Kazuaki Kito, Hitachi-GE Nuclear Energy

Focus: SMR and advanced technologies: technology and policy


Xujia Wang

Xujia Wang is Director of general technology department, SNERDI. He graduated from Tsinghua University with master degree of nuclear science and technology. He has over ten years working experience in the fields of new reactor development/core thermal hydraulic design/accident analysis. He participated the project of CNP300/CAP1000 design, and is engaged on CAP1400/CAP1700 development. Now, he is also in charge of the development of advanced SMRs in SNERDI.

Yu Liu

Yu Liu is a senior research engineer of NPIC (Nuclear Power Institute of China), and acts as the leader of thermal-hydraulic group at the design sub-institute. He obtained his BA and PhD in Nuclear Science and Technology from Tsinghua University, China in 2005 and 2010. He mainly works on thermal-hydraulic design and safety analysis of nuclear power plant. His interesting includes multi-physics and multi-scale coupling, CFD analysis and DNBR online monitoring. Also he is a member to develop self-reliant software of NPIC, which has been used for ACP100 (Small Modular Reactors of China) design.

Dr. Paolo Ferroni

Dr. Paolo Ferroni is a Fellow Engineer in the Advanced Reactor Development group at Westinghouse Electric Company LLC. He is the technical lead for the Westinghouse Lead Fast Reactor, that the company is pursuing as its Next Generation of high-capacity nuclear power plant technology. While at Westinghouse, Dr. Ferroni has worked on several programs focused on the development of advanced technologies for both LWRs and non-LWRs, particularly in the area of advanced fuels and advanced reactor concepts. Dr. Ferroni received a MS in Nuclear Engineering from Turin Polytechnic (Italy) and a PhD in Nuclear Engineering from the Massachusetts Institute of Technology (USA).

Kazuaki Kito

Kazuaki Kito is a senior engineer of Hitachi-GE Nuclear Energy. He has been developing the plant system and thermal-hydraulics of BWRs and other innovative reactors, and he now mainly works on plant system design of a small modular BWR. He received Ph.D degree of engineering from the University of Tokyo in 1998.

Panel Title: V&V of Software Used to Analyze Thermal-Hydraulics in Nuclear Systems

Panel No: 10
Date & Time: Tuesday, July 24, 2018 @ 2 PM
Meeting Room: Epernay Room
Panel Organizer/Leader: Richard Schultz; srr@srv.net


  1. Yassin Hassan, Texas A&M University, USA
  2. Shuo Li, State Nuclear Power Technology Corporation, Beijing
  3. Elia Merzari, Argonne National Laboratory, USA
  4. Hideo Nakamura, Japan Atomic Energy Agency, Tokyo
  5. Sam Treasure (or other participant from Rolls-Royce Ltd)
  6. Participant from UK Nuclear Regulatory; Areva Power; or NEAMS-ART

Abstract: The panelists will discuss the importance, scope, and techniques fundamental to verifying and validating software used to analyze thermal-hydraulics in nuclear systems. Of particular interest are the techniques used to define the matrix of experiments used to validate the software (both systems analysis and CFD) over the nuclear system operational and accident domains. The various scaling techniques employed to design experimental facilities and to achieve the V&V objectives will likely be discussed.


Yassin Hassan

Yassin Hassan is Professor and Head of the Department of Nuclear Engineering, Sallie and Don Davis’61 Professor of Engineering and also Professor of the Department of Mechanical Engineering at Texas A&M University. Prior to joining Texas A&M September 1986, he worked for seven years at Nuclear Power Division, Babcock & Wilcox Company, Lynchburg, Virginia. His research is in computational and experimental thermal hydraulics, reactor safety, laser-based flow visualization and diagnostic imaging techniques, system modeling, multiphase flow, transient and accident analyses and advanced nuclear reactors.

Shuo Li

Shuo Li works for State Power Investment Corporation Research Institute (SPICRI) and National Energy Key Laboratory of Nuclear Power Software in China. The software package COSINE (Core and System Integrated Engine for design and analysis) is developed by SPICRI. He mainly researches in the development and V&V of NPP design software.

Dr. Hideo Nakamura

Dr. Hideo Nakamura is Technical Associate of Nuclear Safety Research Center, Japan Atomic Energy Agency (JAEA) since April 2018. He joined former Japan Atomic Energy Research Institute (JAERI) in 1981 to work for the ROSA (Rig-of-Safety Assessment) program to study thermal-hydraulic phenomena during reactor accidents for both of BWR & PWR with large-scale experiments under reactor prototypical conditions. In 2001, he became a head of Thermo-hydraulic Safety Research Group dedicated for both of severe accident and beyond design-basis accidents. Since 2005, he was a director of operating agent (JAEA) of the OECD/NEA ROSA and ROSA-2 Projects with LSTF experiments. He is an executive editor of Nuclear Engineering and Technology since 2015.