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Signed in July 2001 by Argentina, Brazil, Canada, France, Japan, Korea, South Africa, United Kingdom and United States. Signed in February 2002 by Switzerland and in July 2003 by Euratom.

Parties (as of end of May 2006): Canada, Euratom, France, Japan, Korea, Switzerland, United States

Summary report of the 1st Official SSC jointly with D&S PMB meeting

Summary record

Summary report

Draft presentation from Bob Bari
Draft presentation at the GIF Symposium

Draft submitted by Bob for the EG Review Meeting

10.2.2 R&D status Japan JAEA
10.2.4 R&D status China INET
GIF EG Meeting Beijing
GIF Portal users manual 2013 cvr
GIF Portal users manual 2013 1
GIF EG Meeting Beijing
GIF EG Meeting Beijing a
GIF EG Meeting Beijing b
GIF PG Meeting Beijing
GIF PG Meeting Beijing a
IMG 1979
MSR group file
IMG 1979-425
IMG 1979-25cm
MSR Dimitrovgrad July 2013

Events

Origins of the GIF

Origins of the GIF

Frequently Asked Questions

CDBOP Meeting - Argonne - Aug 2013 (Gerardi)
Moisseytsev SCO2 Control and PDC Validation
September SFR CD BOP PMB Meeting-6
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framework pg
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The first generation of nuclear reactor prototypes were constructed in the 1950s and 60s and culminated in the construction of the first series of civil nuclear power reactors. The construction of the second generation of reactors started at the beginning of the 1970s and marked the widespread appearance of Light Water Reactors (LWR), either Pressurized Water Reactors (PWR) or Boiling Water Reac... more

Framework Agreement Signature

Economic Modelling Working Group (EMWG)

Proliferation Resistance & Physical Protection Working Group (PRPPWG)

Risk & Safety Working Group (RSWG)

Partners External Collaborators

GEN IV Evolution Designs

One of the fundamental goals for Generation IV nuclear energy systems is that they will have a clear life-cycle cost advantage over other energy sources. However, since Generation IV reactors are still at an early stage of development and will not be deployed commercially for at least two to three decades, it is difficult to quantify these cost benefits. In particular, Generation IV systems char... more

Technology Goals

Project Arrangement

Technology Systems

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Technical Secretariat

Technical Secretariat

Technology System: SCWR

System Arrangements

Since they have been designed to operate in a thermal (less energetic) neutron spectrum, current Gen-II and Gen-III Light-Water Reactors (LWRs) can extract fission energy from only a small fraction of the uranium in the fuel (effectively only the "fissile" U-235 component, which makes up less than 1% of natural uranium). Under such conditions, known and easily accessible uranium reserves are cap... more

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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 fourteen Members which are signatories of its founding document, the GIF Charter.

The goals adopted ... more

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FAQ

Gas-Cooled Fast Reactor (GFR)

Gas-Cooled Fast Reactor (GFR)

Lead-Cooled Fast Reactor (LFR)

Lead-Cooled Fast Reactor (LFR)

Molten Salt Reactor (MSR)

Molten Salt Reactor (MSR)

Supercritical-Water-Cooled Reactor (SCWR)

Technology System: SCWR

Sodium-Cooled Fast Reactor (SFR)

Sodium-Cooled Fast Reactor (SFR)

Very-High-Temperature Reactor (VHTR)

Very-High-Temperature Reactor (VHTR)

Education & Training

Partners External Collaborators

Generation IV International Forum Response to the Fukushima Daiichi Nuclear Power Plant Accident

GIF Presentations

R&D Outlook and Technology Roadmap

Publications

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GIF Photo Gallery

Members

Organisation

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desription

John Kelly
Dohee Hahn
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A fast reactor operates in a more energetic neutron spectrum, and is able, via nuclear transformations within the fuel, to "breed" fissile plutonium (Pu-239) from fertile uranium (U-238), which can then be recycled in fresh fuel. In this way, the energetic potential of U-238, representing more than 99% of the original natural uranium, can also be exploited.

Gen IV fast reactor designs will rep... more

Recycling all the minor actinides back into fresh fuel enables them to be "burnt" in the reactor and transformed into so-called fission products. These fission products are separated out from the fuel in the reprocessing plant and constitute the "ultimate" waste from the process. This waste must be managed and ultimately disposed of in line with accepted and approved practice. The radioactivity ... more

Along with the physical and administrative monitoring, control and security measures currently in place, careful selection of the fuel composition and reprocessing techniques may further increase the proliferation resistance of the Gen IV nuclear fuel cycle. Making nuclear material less suitable for use in a nuclear weapon, or less prone to diversion for such use, can be achieved in three differ... more

Sodium is highly compatible with the reactor materials, which essentially rules out corrosion problems for the life of the plant. The first reactor to demonstrate inherent safety features that would eliminate the potential for catastrophic accidents like Fukushima was sodium cooled. Sodium is a highly efficient coolant compared to water, meaning that the system can operate at low pressure and hi... more

Molten lead is a very heavy coolant that provides advantages for radiation shielding, heat removal, and relative compatibility with the steam system. Lead has also been combined with bismuth to form a coolant with a lower melting temperature coolant, which simplifies design and improves operability. Both concepts would operate at low pressure.

Lead presents some unusual engineering challenges.... more

Molten salt has some interesting benefits in reactor design, with unequaled flexibility. On the plus side, molten salt is an efficient high-temperature coolant whose transparency enables inspection and maintenance of components. The reactor fuel can be dissolved in the salt to allow continuous removal of impurities, or the salt can be used to cool more conventional solid fuel. Both concepts woul... more

Within GIF, helium is used as a coolant in two quite different system concepts. Helium has the advantage of being transparent, completely inert, and remains a gas at all temperatures and pressures of interest. Gas-cooled reactors operate at high pressure, but lower than current water-cooled reactors.

For reactor designers, the challenge with helium coolant is that its heat removal and retentio... more

Helium shortages can sometimes appear in the current market because it is thin. If a large market for gas-cooled reactors develops, sufficient helium could be captured from oil well production to satisfy the increased demand. Also, helium would be expected to behave like other commodities — short-term supply restrictions would drive up prices, stimulating more exploration and development.

Ordinary water subjected to very high pressure becomes supercritical water, which has a high boiling temperature, greater density, and enhanced chemical reactivity. Supercritical water has been successfully applied in modern coal plants around the world. Its advantages as a reactor coolant are much higher generating efficiency and a wealth of industrial experience that can be applied.

The disa... more

In 50 years of nuclear energy development and deployment, the safety performance of nuclear power plants has been continuously improved. Some of these improvements are due to adaptation to state-of-the-art, as occurs with all technologies. Others are the result of lessons learnt following incidents and accidents that have occurred (Three Mile Island 1979; Chernobyl, 1986; Fukushima, 2011) and of... more

The Forum is an organization that has a specific goal: the development of concepts for one or more Generation IV systems that can be licensed, constructed, and operated in a manner that will provide a competitively priced and reliable supply of energy to the country or countries where such systems may be deployed, while satisfactorily addressing nuclear safety, waste, proliferation and public pe... more

It will take at least two or three decades before the deployment of commercial Gen IV systems. In the meantime, a number of prototypes will need to be built and operated. The Gen IV concepts currently under investigation are not all on the same timeline and some might not even reach the stage of commercial exploitation.

Examples of advanced reactor prototypes (steps towards Gen IV designs) cu... more

The GIF Experts Group has drafted a position paper on the use of Thorium in the nuclear fuel cycle.

technologies
Dr Aoto

GIF membership

SCWR System Steering Committee

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