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The Generation IV International Forum (GIF) is a co-operative international endeavour which was set up to carry out the research and development 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 selected systems are based on a variety of reactor, energy conversion and fuel cycle technologies. Their designs include thermal and fast neutron spectra cores, closed and open fuel cycles. The reactors range in size from very small to very large. Depending on their respective degree of technical maturity, the first Generation IV systems are expected to be deployed commercially around 2030-2040. 

Evolution Reactor Technology


What's New

GIF Framework Agreement extended for ten years

On 26 February 2015, the Framework Agreement for International Collaboration on Research and Development of Generation IV Nuclear Energy Systems was extended for another ten years, thereby paving the way for continued collaboration among participating countries. A signing ceremony was held at the OECD in Paris in the presence of Mr Angel Gurría, OECD Secretary-General and Depositary of the Framework Agreement, and Mr William D. Magwood, IV, NEA Director-General. The ceremony also featured introductory remarks by Christophe Béhar, CEA Director of the Nuclear Energy Division and Vice-Chair of the GIF Policy Group. For more information, see Framework Agreement.

Upcoming Events

blue triangle The 3rd Generation IV International Forum (GIF) Symposium, in conjunction with the ICONE-23 Conference, will be held at Makuhari Messe in Chiba, Japan on 19-20 May 2015. Visit the ICONE-23 Conference website for further details.

ISSCWR-7 in Finland: A great success

 

ISSCWR-7

The 7th International Symposium on Super-Critical Water-cooled Reactors (ISSCWR-7) was held in Helsinki, Finland on 15-18 March 2015. This biannual Symposium was hosted by VTT Technical Research Centre of Finland in co-operation with the Finnish Network for Generation Four Nuclear Energy Systems (GEN4FIN), the Generation IV International Forum (GIF) , the International Atomic Energy Agency (IAEA) and the Canadian Nuclear Society (CNS). It provided a forum for discussion on advancements and issues, to share information on technical achievements and establish future collaboration on Research and Development for supercritical water-cooled reactors (SCWR). More than 90 participants from 14 different countries representing research organisations, universities and industry were present at this event and 92 presentations were given. All papers were published in a symposium proceeding. A technical visit of the Teollisuuden Voima Oyj (TVO) Olkiluoto site was organised on 19 March 2015. The GIF SCWR Project Management Board and System Steering Committee meetings were held back-to-back with the ISSCWR-7 on 18 and 20 March 2015.

Molten Salt Reactor System Steering Committee (MSR) Meeting

The last Gen IV MSR provisional System Steering Committee meeting was held on 28-29 May 2014 in Shanghai, China. Delegates and observers from France, Euratom, Russia, China, Japan, Korea, and the United States along with guest lecturers from Australia gathered for a two-day meeting and a technical visit of the Molten Salt loop facilities on Jiading Campus at the Shanghai Institute of Applied Physics/Thorium Molten Salt Reactor (TMSR) Centre. On 30 May, following the MSR meeting, participants attended a panel on the “International review meeting of the pre-conceptual design of the 2MW liquid-fueled TMSR”.

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

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