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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 Generation IV International Forum has thirteen Members which are signatories of its founding document, the GIF Charter.

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.

Evolution/Generations of nuclear power

Source: Nuclear Energy Today © OECD/Nuclear Energy Agency 2012

What's New

Just Published: GIF Technology Roadmap Update

The Technology Roadmap Update provides an assessment of progress made by the Generation IV International Forum (GIF) in the development of the six systems selected when the original Technology Roadmap was published in 2002. Learn more and download the publication

Upcoming Events

blue triangle The 3rd GIF Symposium will be held in Japan in May 2015. Further details will be posted here.

Latest progress in the development of VHTR TRISO fuel

Article reproduced courtesy of ANS from Nuclear News, November 2013

The Idaho National Lab (INL) and the Oak Ridge National Lab (ORNL) report on progress made in the development of Tristructural-isotropic (TRISO) fuel with recent post-irradiation tests showing that fuel can retain fission products at 1800°C. Read the article pdf icon

Gen IV News Article
SCWR System Steering Committee Meeting

September 2013 - Petten, The Netherlands

blue triangle 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.



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