Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors

Program and Results of Reactor Tests of Mixed Nitride Fuel for Fast Reactors

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 techno...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2015-06, Vol.118 (2), p.96-100
Hauptverfasser: Troyanov, V. M., Grachev, A. F., Zabud’ko, L. M., Skupov, M. V., Zozulya, D. V.
Format: Artikel
Sprache:eng
Schlagworte:
Assemblies
Coolants
Corrosion
Experiments
Fuels
Hadrons
Heavy Ions
Mixed nitrides
Nuclear Chemistry
Nuclear Energy
Nuclear engineering
Nuclear fuels
Nuclear Physics
Nuclear power generation
Nuclear reactor components
Nuclear reactors
Physics
Physics and Astronomy
Plutonium
Reactors
Research centers
Studies
Uranium
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Beschreibung
Zusammenfassung: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.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-015-9962-0