Education and Training Series #25: SCIENTIFIC AND TECHNICAL PROBLEMS OF CLOSED NUCLEAR FUEL CYCLE IN TWO-COMPONENT NUCLEAR ENERGETICS
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 webinar presents the overview of scientific and technical problems of closed nuclear fuel cycle in two-component nuclear energetics. The presentation will highlight the existing problems of the current technological platform of NE (thermal reactors in an open nuclear fuel cycle) and the advantages of the new technological platform (fast reactors with closed nuclear fuel cycle). Latest developments associated with the use of mixed UN fuel & spent nuclear fuel reprocessing are briefly presented as well. The remaining research challenges of the new technological platform being developed within the “Proryv” Project framework are summarized in the light of the present technology understanding,
Presentation made during the webinar
Meet the presenter
Mr. Alexander Orlov, Ph.D. is the advisor to the Scientific Director of R&D of the “Proryv” Project. Since 2012, he has been a member of the team developing a new technological platform for NE which consists of fast reactors with lead and sodium coolants, a new type of reactor fuel (mixed U-Pu nitride), and technologies to reprocess spent nuclear fuel in order to return it into the fuel cycle. These technologies combined are known as the “Proryv” Project.