Education and Training Series #59: Geometry Design and Transient Simulation of a Heat Pipe Micro Reactor

Date/Hours: 18 November 2021
Location: Online - Free webcast

Part of a webinar series hosted by the GIF Education and Training Working Group since 2016.

Who should attend?
Policymakers, industry professionals, regulators, researchers, students, the general public. 

Webinars
Advanced Manufacturing
Education & Training
Updated on 23/11/2024

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

In recent years, micro-reactor concepts have attracted increasing attention in the nuclear industry due to the market demand for flexible, reliable, and sustainable power and heat on-site for industrial or federal installations or remote communities. Micro-reactor AGile Non-nuclear Experimental Test-bed (MAGNET) is at Idaho National Laboratory (INL) with an initial focus on the thermal and structural performance of heat pipe cooled micro-reactors. System Analysis Module (SAM) code is a multi-dimensional modern software tool provided by Argonne National Laboratory (ANL). This webinar will review the designs of heat-pipe micro reactors, steady-state and transient simulation of MAGNET by SAM, to explore the performance limit by heat transfer and temperature distribution.

Recording of the Webinar

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Presentation made during the webinar

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Meet the presenter

Jun Wang, Ph.D., is an associate scientist of Nuclear Engineering and Engineering Physics at the University of Wisconsin-Madison. Wang gets his Ph.D. from Xi’an Jiaotong University. His research interests include the advanced numerical analysis of nuclear safety and reliability for various reactor designs. Wang is leading a few projects on the heat pipe micro reactor, high temperature gas cooled reactor transient analysis, and uncertainty quantification by artificial intelligence. Wang also serve the ANS thermal hydraulics committee, and the journal Progress in Nuclear Energy, Annals of Energy Research as editorial board.