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The first GIF provisional System Steering Committee for Lead Fast Reactors (LFR pSSC) was established after the LFR Memorandum of Understanding was signed in 2010. In 2025, under the new 2025 GIF Framework Agreement, a new version of the GIF LFR MoU was opened for signature. It will become effective once three signatures are gathered. The resulting committee is aimed at exploring a broad range of topics related to Lead Fast Reactors. One LFR is currently under construction and about a dozen are under development around the world. 

The Proliferation Resistance and Physical Protection Working Group (PRPPWG) was established to develop, implement, and foster the use of an evaluation methodology to assess Generation IV (Gen-IV) nuclear energy systems with respect to the GIF proliferation resistance (PR) and physical protection (PP) goal:

“Generation IV nuclear energy systems will increase the assurance that they are very unattractive and the least desirable route for diversion or theft of weapons-usable materials and provide increased physical protection against acts of terrorism.”

The “Non-Electric and Cogeneration Applications of Nuclear Energy” Working Group (NECA WG) was formed in 2024 to advance knowledge and access to energy system design, analysis, and optimisation tools that may allow decision makers to find optimal energy system solutions for different socio-economic and geographical contexts. This working group builds upon the work carried by the concluded GIF Non-Electric Applications of Nuclear Heat (NEANH TF, 2021-2024).

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%.

For over twenty years, the Generation IV International Forum (GIF) has supported global cooperative initiatives to develop advanced nuclear energy systems addressing future global energy requirements. The objectives set for Generation IV designs encompass enhanced fuel efficiency, minimized waste generation, economic competitiveness, and adherence to rigorous safety and proliferation resistance measures. 

Initially, GIF conducted a comprehensive review of reactor technologies, eventually focusing on six promising technologies. 

On this page you will find the list of all the GIF Webinars.

The first table lists all the Webinars from the Education and Training series.

The second table lists all the Webinars from the GIF Talks with Industry series.