Education and Training Series #18: MATERIALS CHALLENGES FOR GEN IV REACTORS
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.
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
The Generation IV reactors offer significant advantages over typical light water reactors including increased power conversion efficiency, passive safety features and in some cases process heat for other applications (e.g. hydrogen production). These families of reactors include 3 fast reactors [sodium fast reactor (SFR), lead fast reactor (LFR) and gas-cooled fast reactor (GFR)], one thermal reactor [very high temperature reactor (VHTR)] and two fast or thermal reactors [supercritical water reactor (SCWR) and molten salt reactor (MSR)]. The extreme environments in these families of reactors create significant challenges to materials ranging from high doses from a fast neutron flux (SFR, LFR, GFR, SCWR and MSR), more corrosive environments from molten salt (MSR) or lead coolants (LFR) and high temperatures in the helium-cooled reactor concepts (e.g. GFR and VHTR). This presentation will discuss the materials challenges in Gen IV reactor concepts and summarize radiation effects in reactor metals proposed for these concepts over prototypic irradiation conditions.
Presentation made during the webinar
Meet the presenter
Stuart Maloy is a Team Leader for MST-8 (materials at radiation and dynamic extremes) at Los Alamos National Laboratory(where he has worked for 28 years) and is the advanced reactor core materials technical leader for the Nuclear Technology Research and Development’s Advanced Fuels campaign and the NEET Reactor Materials Technical Lead for DOE-NE. He earned his Bachelors Degree (’89), Masters Degree (’91) and PhD (’94) in Materials Science from Case Western Reserve University and is a registered PE in Metallurgy. He has applied his expertise to characterizing and testing the properties of metallic and ceramic materials in extreme environments such as under neutron and proton irradiation at reactor relevant temperatures. This includes testing the mechanical properties (fracture toughness and tensile properties) of Mod 9Cr-1Mo, HT-9, 316L, 304L, Inconel 718, Al6061- T6 and Al5052 after high energy proton and neutron irradiations using accelerators and fast reactors. Characterization of materials after testing includes using transmission electron microscopy for analyzing defects such as dislocations, twins and second phases, using high resolution electron microscopy to characterize defects at an atomic level and nanoscale mechanical testing. Stuart has >190 peer reviewed technical publications and numerous presentations.