Education and Training Series #102: Thermal hydraulics of Supercritical pressure water-cooled Reactor (SCWR)
This webinar is part of a series hosted by the GIF Education and Training Working Group since 2016.
The link to register to this webinar can be found on this page under "about this webinar".
Who should attend?
Policymakers, industry professionals, regulators, researchers, students, the general public.
Supercritical pressure water-cooled reactors (SCWRs) have garnered significant interest from the international nuclear community due to their potential for high thermal efficiency and substantial plant simplification. SCWRs are the sole water-cooled reactor among the six GEN-IV concepts. Over the past decade, extensive research activities on SCWRs have been conducted in the nuclear industry. This presentation summarizes and reviews various R&D activities, including experimental studies, analytical methods, and numerical simulations, related to SCWR development. It also identifies future R&D challenges. These efforts contribute to a better understanding of the fundamental thermal-hydraulic phenomena and the improvement of prediction methods.
Dr. Patricia Paviet from PNNL, USA, member of GIF ETWG will facilitate this webinar.
About the "GIF Education and Training" Webinars
These webinars, organised by the GIF Education and Training Working Group are streamed live monthly. The recordings and slide decks are accessible after the webinar on this website. These webinars cover a very broad range of technical and policy related topics. At the end of 2023 they have been viewed by more than 15000 people (approximately half of the views during the live streams and the other half views being of the archives on the public GIF website). In total, the GIF webinars have reached Generation IV enthusiasts, scientists, and engineers in more than 80 countries.
These webinars are organised and hosted by the GIF Education and Training Working Group (ETWG).
About this Webinar
Supercritical pressure water-cooled reactors (SCWRs) have garnered significant interest from the international nuclear community due to their potential for high thermal efficiency and substantial plant simplification. SCWRs are the sole water-cooled reactor among the six GEN-IV concepts. Over the past decade, extensive research activities on SCWRs have been conducted in the nuclear industry. This presentation summarizes and reviews various R&D activities, including experimental studies, analytical methods, and numerical simulations, related to SCWR development. It also identifies future R&D challenges. These efforts contribute to a better understanding of the fundamental thermal-hydraulic phenomena and the improvement of prediction methods.
Dr. Patricia Paviet from PNNL, USA, member of GIF ETWG will facilitate this webinar.
Presentation of the webinar
Meet the presenter
Pr
Xiaojing Liu
Professor Xiaojing Liu from Shanghai Jiao Tong University in China obtained his Ph.D. degree from SJTU in 2010. He was a postdoctoral fellow at the Karlsruhe Institute of Technology (KIT) in Germany from 2012 to 2013. He is currently the director of the Shanghai integrating innovation center for digital reactors, leader of the Innovative Nuclear System Laboratory (INSL) in SJTU and has long been engaged in research on advanced and digital nuclear energy systems. He has published over 200 papers in renowned journals such as Applied Energy, Energy Conversion and Management, and Annals of Nuclear Energy.
He serves as a board member of the Nuclear Reactor Thermal-Hydraulics Division of the Chinese Nuclear Society, Associate editor of ASME Journal of Nuclear Engineering and Radiation Science (JNERS), Editorial Advisory Board member of Nuclear Engineering and Design, Youth editorial board member of Nuclear Science and Techniques and Frontiers in Energy.