Innovative Technological Center for the Proryv Project

Moscow, Russia

Innovative Technological Center for the Proryv Project

Moscow, Russia
SEARCH FILTERS
Time filter
Source Type

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

Loading Innovative Technological Center for the Proryv Project collaborators
Loading Innovative Technological Center for the Proryv Project collaborators