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Troyanov V.M.,Innovative Technological Center for the Proryv Project | Grachev A.F.,Innovative Technological Center for the Proryv Project | Zabud'ko L.M.,Innovative Technological Center for the Proryv Project | Skupov M.V.,Russia Research Institute of Inorganic Materials | Zozulya D.V.,Siberian Chemical Combine SKhK
Atomic Energy | Year: 2015

In the Proryv project, mixed uranium-plutonium nitride fuel is to be used in the future nuclear power with fast reactors with sodium coolant (BN-1200) and with lead coolant (BREST). At present, experimental fuel elements and fuel assemblies with mixed nitride fuel are fabricated by means of a technology developed at the Bochvar All-Russia Research Institute for Inorganic Materials for testing in the BN-600 reactor and the MIR and BOR-60 research reactors. The program of reactor tests of the experimental fuel assemblies and some preliminary results of these tests are presented. © 2015 Springer Science+Business Media New York Source

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