The Generation IV International Forum (GIF) is a co-operative international endeavour organised to carry out the research and development (R&D) needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems.
The goals adopted by GIF provided the basis for identifying and selecting six nuclear energy systems for further development. The six selected systems employ a variety of reactors, energy conversion and fuel cycle technologies. Their designs feature thermal and fast neutron spectra, closed and open fuel cycles and a wide range of reactor sizes from very small to very large. Depending on their respective degrees of technical maturity, the Generation IV systems are expected to become available for commercial introduction around 2030-2040.
The Generation IV International Forum (GIF) Super-Critical Water-cooled Reactor (SCWR) System Steering Committee (SSC) held its 2nd meeting of the year in Petten, the Netherlands, hosted by the European Commission Joint Research Centre.
Six months after meeting in Shenzhen, China, following the successful 6th International Symposium on Super-Critical Water-cooled Reactors (ISSCWR-6), the SCWR SSC made progress in defining the updated Project Plans over the next five years for the Thermal-Hydraulics and Safety Project Arrangement and the Materials and Chemistry Project Arrangement.Collaborative research is being performed in both projects with an on-going benchmarking exercise for computational tools on supercritical heat transfer in a 7-rod bundle, and a round-robin testing exercise for materials under supercritical conditions at many institutions in Europe, Canada and Japan. Members of the SCWR SSC requested chairs of the Project Management Boards to initiate the preparation of the Annual Work Plan for 2014. The organization of the 7th International Symposium on SCWRs (ISSCWR-7) in 2015 was also discussed.
Molten Salt Reactor Steering Committee Meeting
July 2013 - Dimitrovgrad, Russia
The Generation IV International Forum (GIF) Molten Salt Reactor (MSR) System Steering Committee (SSC) held its semi-annual meeting on 2-4 July 2013 in Dimitrovgrad, Russia.
The meeting featured technical progress updates from all of the participating counties as well as a daylong technical visit to the nearby Research Institute of Atomic Reactors (RIAR). This was the first MSR SSC meeting that representatives from the Republic of Korea participated in. Russian MSR development efforts were emphasized in both the meeting and the technical tours including providing a demonstration of fissile material solubility measurements in molten salt. The meeting featured a number of technical discussions including: the impacts of the updated GIF technology roadmap that now explicitly includes salt cooled as well as salt fueled reactors, developing a common MSR safety evaluation approach, progress on MSR technology and materials development roadmaps, as well as improving MSR SSC communications through updating the public website.
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Disclaimer: The information contained in the GIF website and in documents that can be downloaded from the GIF website is aimed primarily at the general public and at those that have an interest in the research and development of Generation IV nuclear energy systems. The opinions expressed and arguments employed in this information do not necessarily reflect the official views of the GIF or the governments or national governmental agencies of their respective members. The GIF or the governments or national governmental agencies of their respective members, or any person acting on their behalf, make no statements, representations or warranties about the accuracy, completeness or reliability of this information and none may be held responsible for any use that may be made of it.