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The OECD Nuclear Energy Agency has been supporting the activities of the Generation IV International Forum since 2005. It provides technical secretariat services, archiving records and documents, as well as maintaining the Forum's internal and external websites. The NEA Technical Secretariat consists of more than 12 staff members on both a full-time and part-time basis.

The GFR system is a high-temperature helium-cooled fast-spectrum reactor with a closed fuel cycle. It combines the advantages of fast-spectrum systems for long-term sustainability of uranium resources and waste minimisation (through fuel multiple reprocessing and fission of long-lived actinides), with those of high-temperature systems (high thermal cycle efficiency and industrial use of the generated heat, for hydrogen production for example).

LFR (Lead-cooled Fast Reactor) systems are reactors cooled by liquid lead (Pb) or, in very few cases, by lead-bismuth (Pb-Bi) alloy and operating in the fast neutron spectrum at atmospheric pressure and high temperature. Many advantages of the LFR system are related to its choice of coolant: lead has a very high boiling point (up to 1743°C), favorable neutronic and radiation shielding properties as well as its benign interaction with water and air. 

The Sodium-cooled Fast Reactor (SFR) utilizes liquid sodium as a coolant and functions within the fast neutron spectrum, which facilitates a high power density and the advantage of low-pressure operation. Despite ongoing challenges in its development, SFRs draw on the collective experience of over 20 reactors globally, amounting to more than 400 reactor-years of operation. This extensive experience has progressively improved the safety and reliability of these reactors.

The Very High Temperature Reactor (VHTR), one of six Gen IV nuclear system candidates, is designed for electricity and heat cogeneration, and its high outlet temperature is ideal for hydrogen production and use in the chemical, oil, and iron industries. Drawing on operational experience from past or operating gas-cooled reactors in five countries, the VHTR features TRi-structural ISOtropic (TRISO) fuel, helium coolant, and low power density that supports passive decay heat removal.

Molten Salt Reactors (MSRs) are a class of nuclear fission reactors where molten salts serve as the reactor fuel, coolant, and / or moderator. Research on MSRs began early in the development of nuclear energy. These reactors can operate at lower pressures (ambient) and higher temperatures compared to conventional water-cooled reactors.

SuperCritical Water-Cooled Reactors (SCWRs) are advanced nuclear reactors operating at temperatures and pressures above water's critical point (374°C, 22.1 MPa). SCWRs can feature thermal, fast, or mixed neutron spectra and are designed in two configurations: pressure vessel (similar to BWRs and PWRs) and pressure tubes (like CANDU reactors). Combining design insights from existing water-cooled reactors and supercritical fossil-fired plants, SCWRs achieve higher thermal efficiencies of 44-48%, significantly improving over the current 34-36%.

The Sodium Fast Reactor System Steering Committee (SFR SSC) was initially formed following the signing of the SFR System Arrangement in 2006 under the now expired 2005 GIF Framerwork Agreement. A new SFR SA has been opened for signatures under the new 2025 GIF FA and became effective in March 2025. This committee supervises five projects encompassing a wide array of subjects pertaining to Sodium Fast Reactors. Until recently, the SFR System was the sole system with commercially operating reactors globally.

The Gas-cooled Fast Reactor System Steering Committee (GFR SSC) was initially formed following the signing of the GFR System Arrangement in 2006. A new version of the GFR System Arrangement (SA) has been signed in 2025 under the new GIF 2025 Framework Agreement. Currently, two members of the Generation IV International Forum (GIF) have signed the new GFR SA. The GFR SSC supervises two projects encompassing a wide array of subjects pertaining to Gas-cooled Fast Reactors.

The Super Critical Water Reactors System Steering Committee (SCWR SSC) was initially formed following the signing of the SCWR System Arrangement in 2006. This FA expired in early 2025. A new SCWR FA has been proposed under the current 2025 GIF FA. It will become effective once three signatories are gathered. The resulting committee goal is to supervise four projects encompassing a wide array of subjects pertaining to Super Critical Water Reactors.

The Very High Temperature Reactor System Steering Committee (VHTR SSC) was initially established under the now expired 2005 GIF Framework Agreement after the VHTR System Arrangement was signed in 2006. The new VHTR SA became effective in 2025 under the new 2025 GIF Framework Agreement. This committee oversees four projects that cover a broad range of topics related to Very High Temperature Reactors. The VHTR, along with Sodium Fast Reactors, is one of the Generation IV systems that has commercial-scale power reactors in operation today and has also had several in operation previously.