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The reactor uses a plutonium-uranium mixed carbide fuel and liquid sodium as a coolant. The fuel is an indigenous mix of 70 percent plutonium carbide and 30 percent uranium carbide. Plutonium for the fuel is extracted from irradiated fuel in the Madras power reactors and reprocessed in Tarapur.
Clementine was the code name for the world's first continuous [note 1] fast-neutron reactor, also known as the Los Alamos fast plutonium reactor. It was an experimental-scale reactor. The maximum output was 25 kW and was fueled by plutonium and cooled by liquid mercury. Clementine was located at Los Alamos National Laboratory in Los Alamos, New ...
The first fast reactor built and operated was the Los Alamos Plutonium Fast Reactor ("Clementine") in Los Alamos, NM. [14] Clementine was fueled by Ga-stabilized delta-phase Pu and cooled with mercury. It contained a 'window' of Th-232 in anticipation of breeding experiments, but no reports were made available regarding this feature.
The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.
In a 2008 paper, Kessler et al. used a thermal analysis to conclude that a hypothetical nuclear explosive device was "technically unfeasible" using reactor grade plutonium from a reactor that had a burn up value of 30 GWd/t using "low technology" designs akin to Fat Man with spherical explosive lenses, or 55 GWd/t for "medium technology" designs.
France had considered the problem of plutonium production just after the end of World War II. At the time, the conventional solution to this problem was to use a graphite moderated air or water cooled reactor fueled with natural uranium. Such designs have little economic value in terms of power production, but are simple solutions to the ...
The Zero Power Physics Reactor or ZPPR (originally named Zero Power Plutonium Reactor) was a split-table-type critical facility located at the Idaho National Laboratory, Idaho, USA. [1] It was designed for the study of the physics of power breeder systems and was capable of simulating fast reactor core compositions characteristic of 300-500 MWe ...
The reactor is part of the final step for a plutonium-burner core (a core designed to burn and, in the process, destroy, and recover energy from, plutonium) [4] The plant reached its full power production in August 2016. [5]