IFMIF: Difference between revisions

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The '''International Fusion Material Irradiation Facility''', also known as '''IFMIF''', is an international scientific research program designed to test materials for suitability for use in a [[Fusion reactor|fusion reactor]]. The IFMIF, planned by Japan, the European Union, the United States, and Russia, and managed by the [[International Energy Agency]], will use a particle accelerator-based neutron source to produce a large neutron flux, in a suitable quantity and time period to test the long-term behavior of materials under conditions similar to those expected at the inner wall of a fusion reactor.
The International Fusion Material Irradiation Facility (IFMIF <ref>[http://www.frascati.enea.it/ifmif/ IFMIF website]</ref>) is an international scientific research program designed to test materials for suitability for use in a [[Fusion reactor|fusion reactor]]. The IFMIF, planned by Japan, the European Union, the United States, and Russia, and managed by the International Energy Agency,<ref>[http://www.iea.org/ IEA website]</ref> will use a particle accelerator-based neutron source to produce a large neutron flux, in a suitable quantity and time period to test the long-term behavior of materials under conditions similar to those expected at the inner wall of a fusion reactor.
 
== See also ==


==See also==
* [[IFMIF-EVEDA]]
* [[IFMIF-EVEDA]]
* [[ITER]]


==External links==
== References ==
* [http://www.frascati.enea.it/ifmif/ IFMIF home page]
<references />
* [http://www.iter.org/a/n1/downloads/construction_schedule.pdf ITER schedule]

Revision as of 18:50, 6 September 2009

The International Fusion Material Irradiation Facility (IFMIF [1]) is an international scientific research program designed to test materials for suitability for use in a fusion reactor. The IFMIF, planned by Japan, the European Union, the United States, and Russia, and managed by the International Energy Agency,[2] will use a particle accelerator-based neutron source to produce a large neutron flux, in a suitable quantity and time period to test the long-term behavior of materials under conditions similar to those expected at the inner wall of a fusion reactor.

See also

References