Description
Chairs: Tanju Sofu and Xiaoyan Yang; Anton Moisseytsev
The six Generation IV reactor concepts that have been selected by the GIF members present a diverse set of design and safety characteristics. The Risk & Safety Working Group (RSWG) was formed within the GIF to promote a consistent and effective approach to assuring the safety of Generation IV nuclear energy systems.
Gen IV reactors are significantly different from the earlier generation of...
The International Atomic Energy Agency (IAEA) is reviewing the applicability of the IAEA safety standards to novel advanced reactors including fast reactors. The applicability review first relies on the identification of areas of novelty in the lifecycle of the novel advanced reactors when compared with land based water-cooled large reactors. The paper presents examples of areas of novelty...
The Generation IV International Forum (GIF) Lead Fast Reactor (LFR) provisional System Steering Committee (pSSC) has assessed, in collaboration with the GIF Risk and Safety Working Group (RSWG), the safety characteristics of reference Generation IV LFR systems. The objective has been to review and identify the main safety advantages and potential challenges of the technology, to assess the...
Following the significant scientific results and knowledge acquired from the ASTRID collaboration, the French and Japanese partners launched a new consolidation phase on the technical knowledge on sodium-cooled fast reactors (SFR) and R&D basis to maintain skills and further develop advanced technologies. After signature of an Implementing Arrangement covering the period 2020-2024 (IA2020),...
The ARC-100 is an innovative 100 MWe sodium cooled fast reactor design being developed by Advanced Reactor Concepts (ARC), LLC. The reactor employs a long-lived metallic-fueled core with low burnup reactivity swing, which facilitates citing in remote locations and/or small grids with minimal reactor maintenance during its lifetime. Argonne National Laboratory has been tasked with the safety...
After official notification to the Romanian regulatory authority, CNCAN, about the intention to build the Advanced Lead-cooled Fast Reactor European Demonstrator (ALFRED) at the Mioveni nuclear platform, the Fostering ALFRED Construction (FALCON) international consortium – leading the project – and CNCAN agreed to initiate a formal pre-licensing phase for the project. This choice was deemed...
Within the GIF sodium-cooled fast reactor (SFR) system arrangement, the SFR Safety and Operation (SO) project addresses the areas of safety technology and reactor operation technology developments. The aim of the SO project includes (1) analyses and experiments that support establishing safety approaches and validating performance of specific safety features, (2) development and verification...
ESFR SMART is a European R&D project relating to the safety of sodium-cooled fast reactors, which follows the European R&D project CP ESFR. One of the goals is to seek design improvements taking into account in particular the lessons of the Fukushima accident.
The concept of practical elimination consists, through an appropriate design, in making accidents with inacceptable consequences and...
The Versatile Test Reactor (VTR) is a fast spectrum test reactor currently being developed in the United States under the direction of the US Department of Energy (USDOE), Office of Nuclear Energy. The mission of the VTR is to enable accelerated testing of advanced reactor fuels and materials required for advanced reactor technologies. The conceptual design of the 300 MWth sodium-cooled...
