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    GIF carries out its mission through its Generation IV technology specific System Steering Committees and works on cross cutting and methodological matters through its Working Groups and Task Forces. 

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      • GFR SSC
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  • Generation IV Criteria and Technologies

    Get an overview of how Gen IV Nuclear Energy Systems are defined, what are the Generation IV criteria, which Nuclear Reactors Technologies were selected as capable of meeting those criteria and how this relates to the GIF Technology Roadmap (and its revisions).

    • Lead Fast Reactors (LFR)
    • Molten Salt Reactors (MSR)
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  • About GIF

    Generation IV International Forum (GIF) was created as a co-operative international endeavour seeking to develop the research necessary to test the feasibility and performance of fourth generation nuclear systems, and to make them available for industrial deployment by 2030. Learn more about its governing agreements and structure here. 

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Super Critical Water Reactors (SCWR)

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%.

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Industry Engagement

GIF is initially a Research and Development (R&D) cooperation plateform driven by members states and their national laboratories.

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Reports
12 May 2018

Preparing the Future through Innovative Nuclear Technology - Outlook for Generation IV technologies - 2018

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Reports
PR&PP
MSR
01 December 2023

Molten Salt Reactors - Proliferation Resistance and Physical Protection White Paper - 2023

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Reports
NECA
30 May 2025

System Analysis: Hydrogen production from nuclear energy

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Reports
PR&PP
26 December 2025

Proliferation Resistance and Physical Protection Siting Study for Advanced Modular Reactors (AMRs) and Microreactors - 2025

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Reports
PR&PP
Safety
VHTR
26 December 2025

Case Study of Safety, Security and Safeguards (3S) Interfaces for a Very High Temperature Reactor System - 2025

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Reports
PR&PP
30 September 2024

Proliferation Resistance and Physical Protection (PR&PP) Bibliography - Revision 11 - 2024

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Reports
Safety
VHTR
01 June 2023

Safety Design Criteria for Generation IV Very High Temperature Reactor System - 2023

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Reports
Safety
01 June 2023

A Risk-Informed Framework for Safety Design of Generation IV Systems - 2023

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Reports
Safety
GFR
01 September 2022

Safety Design Criteria For Generation IV Gas-Cooled Fast Reactor System - 2022

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Reports
Safety
GFR
01 September 2022

Gas-Cooled Fast Reactor System Safety Assessment - 2022

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Reports
Safety
LFR
01 March 2021

Safety Design Criteria for Generation IV Lead-Cooled Fast Reactor System - 2021

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Reports
LFR
Safety
03 June 2020

Lead-cooled Fast Reactor (LFR) System Safety Assessment - 2020

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Reports
SFR
Safety
01 August 2019

Safety Design Guidelines On Safety Approach And Design Conditions for Generation IV Sodium-Cooled Fast Reactor Systems - 2019 - Rev. 1

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Reports
SCWR
Safety
11 July 2018

Supercritical-water-cooled reactor system (SCWR) System Safety Assessment - 2018

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Reports
SFR
Safety
11 April 2017

Sodium-Cooled Fast Reactor (SFR) System Safety Assessment - 2017

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Reports
Safety
SFR
30 September 2017

Safety Design Criteria for Generation IV Sodium cooled Fast Reactor System - 2017 - Rev. 1

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