Open main menu
Home
Random
Recent changes
Special pages
Community portal
Preferences
About Wikipedia
Disclaimers
Incubator escapee wiki
Search
User menu
Talk
Dark mode
Contributions
Create account
Log in
Editing
Integral fast reactor
(section)
Warning:
You are not logged in. Your IP address will be publicly visible if you make any edits. If you
log in
or
create an account
, your edits will be attributed to your username, along with other benefits.
Anti-spam check. Do
not
fill this in!
{{short description|Nuclear reactor design}} [[File:ANLWFuelConditioningFacility.jpg|thumb|upright=1.5|[[Experimental Breeder Reactor II]], which served as the prototype for the integral fast reactor (IFR)]] The '''integral fast reactor''' ('''IFR'''), originally the '''advanced liquid-metal reactor''' ('''ALMR'''), is a design for a [[nuclear reactor]] using [[fast neutron]]s and no [[neutron moderator]] (a [[fast-neutron reactor|"fast" reactor]]). IFRs can breed more fuel and are distinguished by a [[nuclear fuel cycle]] that uses [[nuclear reprocessing#Pyroprocessing|reprocessing]] via [[electrorefining]] at the reactor site. The IFR was a [[sodium-cooled fast reactor]] (SFR) is its closest surviving [[fast breeder reactor]], a type of [[Generation IV reactor]]. The [[U.S. Department of Energy]] (DOE) began designing an IFR in 1984 and built a prototype, the [[Experimental Breeder Reactor II]]. On April 3, 1986, two tests demonstrated the safety of the IFR concept. These tests simulated accidents involving loss of [[coolant]] flow. Even with its normal shutdown devices disabled, the reactor shut itself down safely without overheating anywhere in the system. The IFR project was canceled by the [[US Congress]] in 1994, three years before completion.<ref name=ANL>[http://www.ne.anl.gov/About/reactors/integral-fast-reactor.shtml The IFR] at [[Argonne National Laboratory]], ''www.ne.anl.gov'', accessed 1 November 2022</ref> [[S-PRISM]] (from SuperPRISM), also called PRISM (power reactor innovative small module), is the name of a nuclear power plant design by [[GE Hitachi Nuclear Energy]] based on the IFR.<ref>{{cite web |url=http://www.genewscenter.com/Press-Releases/GE-Hitachi-Nuclear-Energy-Encourages-Congress-to-Support-Development-of-Recycling-Technology-to-Turn-Used-Nuclear-Fuel-into-an-Asset-1b9f.aspx |title=GE Hitachi Nuclear Energy Encourages Congress to Support Development of Recycling Technology to Turn Used Nuclear Fuel into an Asset β GE Energy press release |publisher=Genewscenter.com |date=2009-06-18 |access-date=2014-01-24 |url-status=dead |archive-url=https://web.archive.org/web/20131203015654/http://www.genewscenter.com/Press-Releases/GE-Hitachi-Nuclear-Energy-Encourages-Congress-to-Support-Development-of-Recycling-Technology-to-Turn-Used-Nuclear-Fuel-into-an-Asset-1b9f.aspx |archive-date=2013-12-03 }}</ref> In 2022, GE Hitachi Nuclear Energy and [[TerraPower]] began exploring locating five ''Natrium'' SFR-based nuclear power plants in [[Kemmerer, Wyoming]]; the design incorporates a PRISM reactor plus TerraPower's Traveling Wave design with a molten salt storage system.<ref>{{Cite web |title=Natrium |url=https://www.nrc.gov/reactors/new-reactors/advanced/licensing-activities/pre-application-activities/natrium.html |access-date=2022-10-28 |website=NRC Web |language=en-US}}</ref><ref>{{Cite web |last=Patel |first=Sonal |date=2022-10-27 |title=PacifiCorp, TerraPower Evaluating Deployment of Up to Five Additional Natrium Advanced Reactors |url=https://www.powermag.com/pacificorp-terrapower-evaluating-deployment-of-up-to-five-additional-natrium-advanced-reactors/ |access-date=2022-10-27 |website=POWER Magazine |language=en-US}}</ref>
Edit summary
(Briefly describe your changes)
By publishing changes, you agree to the
Terms of Use
, and you irrevocably agree to release your contribution under the
CC BY-SA 4.0 License
and the
GFDL
. You agree that a hyperlink or URL is sufficient attribution under the Creative Commons license.
Cancel
Editing help
(opens in new window)