Ad
related to: sodium 23 fast reactor oil ratio test
Search results
Results From The WOW.Com Content Network
Pool type sodium-cooled fast reactor (SFR) A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor.
The Fast Flux Test Facility with labels. Commemorative photo marking the completion of the FFTF system. The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not generate electricity. It is situated in the 400 Area of the Hanford Site, which is located ...
Sodium-cooled fast reactor based on the existing LMFBR and integral fast reactor designs. Lead-cooled fast reactor based on Soviet naval propulsion units. FBRs usually use a mixed oxide fuel core of up to 20% plutonium dioxide (PuO 2 ) and at least 80% uranium dioxide (UO 2 ).
For the discontinued limited express train service, see Monju (train). Monju (もんじゅ) was a Japanese sodium-cooled fast reactor, located near the Tsuruga Nuclear Power Plant, Fukui Prefecture. Its name is a reference to Manjusri. Construction started in 1986 and the reactor achieved criticality for the first time in April 1994.
The integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator (a "fast" reactor). IFRs can breed more fuel and are distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.
The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe sodium-cooled, fast breeder reactor that is being constructed at Kokkilamedu, near Kalpakkam, in Tamil Nadu state, India. [4] The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible for the design of this reactor, the Advanced Fuel Fabrication Facility at the Bhabha Atomic ...
[23] [24] In February 2022, it was announced that the two companies had agreed to build a demonstration fast-spectrum salt reactor at Idaho National Laboratory (INL). [25] In 2023, the US Department of Energy announced a project to build a test reactor using high-enriched fuel (HEU) containing as much as 90% 235
Jōyō (nuclear reactor) Jōyō (常陽) is a test sodium-cooled fast reactor located in Ōarai, Ibaraki, Japan, operated by the Japan Atomic Energy Agency. The name comes from the previous country name of the area around Ibaraki. It was made with the purpose of doing tests on and advancing the development of that type of reactor, as an ...