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A thermal-neutron reactor is a nuclear reactor that uses slow or thermal neutrons. ("Thermal" does not mean hot in an absolute sense, but means in thermal equilibrium with the medium it is interacting with, the reactor's fuel, moderator and structure, which is much lower energy than the fast neutrons initially produced by fission.)
The BOR-60 reactor was constructed to perform tests for the commercial BN-350, BN-600 and BN-800 reactors, which also use fast neutron breeding. [4] Construction began in 1964, and it reached first criticality in 1968. [4]
A neutron research facility is most commonly a big laboratory operating a large-scale neutron source that provides thermal neutrons to a suite of research instruments. The neutron source usually is a research reactor or a spallation source.
In September, Superphénix, the largest fast reactor and breeder reactor ever, at 1,242 MWe, achieves criticality at Creys-Malville in France. [129] 1986. On April 26, in the Ukrainian SSR, Chernobyl Nuclear Power Plant Unit 4 experiences a core meltdown during a test, the first Level 7 nuclear accident on the International Nuclear Event Scale ...
Most reactor designs in existence are thermal reactors and typically use water as a neutron moderator (moderator means that it slows down the neutron to a thermal speed) and as a coolant. But in a fast breeder reactor, some other kind of coolant is used which will not moderate or slow the neutrons down much. This enables fast neutrons to ...
Chicago Pile-5 (CP-5) was the last of the line of Chicago Pile research reactors which started with CP-1 in 1942. The first reactor built on the Argonne National Laboratory campus in DuPage county, it operated from 1954-1979. [1] CP-5 was a thermal-neutron reactor using enriched uranium as fuel and heavy water as coolant
Self Powered Neutron Detector; Steam-Generating Heavy Water Reactor; Shippingport Atomic Power Station; Shutdown (nuclear reactor) SOS: The San Onofre Syndrome; List of nuclear power systems in space; Startup neutron source; Steam separator; Subcritical reactor
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 .