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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.
Energy portal; Nuclear technology portal; Russia portal; MBIR - multi-loop research reactor intends to replace BOR-60. In construction since 2015, est. completion in 2027. BN-800 reactor - generation IV sodium-cooled fast breeder reactor, operational since 2016
The BN-1200 reactor is a sodium-cooled fast breeder reactor project, under development by OKBM Afrikantov in Zarechny, Russia. The BN-1200 is based on the earlier BN-600 and especially BN-800, with which it shares a number of features. The reactor's name comes from its electrical output, nominally 1220 MWe.
Sodium-cooled fast reactor; Superphénix; V. VT-1 reactor This page was last edited on 16 August 2018, at 00:35 (UTC). Text is available under the Creative Commons ...
The BN-800 reactor (Russian: реактор БН–800) is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. The reactor is designed to generate 880 MW of electrical power.
The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian province, China, on Changbiao Island. [ 1 ] [ 2 ] It is a generation IV demonstration project by the China National Nuclear Corporation (CNNC).
A cutaway model of the reactor. The core, that is the nuclear fuel at the heart of the reactor has dimensions of 2 meters in height by 0.75 meters in diameter, similar to the BN-800 reactor. [1] The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia.
Gas-cooled fast reactor cooled by helium. 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).
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