Entity

Time filter

Source Type


Troyanov V.M.,Innovation and Technology Center for Proryv Project | Grachev A.F.,Innovation and Technology Center for Proryv Project | Zabud'ko L.M.,Innovation and Technology Center for Proryv Project | Skupov M.V.,Russia Research Institute of Inorganic Materials
Atomic Energy | Year: 2014

The present status of research on dense nitride fuel for liquid-metal cooled fast reactors is examined. It is noted that within the framework of project Proryv nitride fuel is to be used in reactors with sodium (BN-1200) as well as lead coolant (BREST). Carbothermal synthesis of nitride from oxide powders has been chosen to fabricate the experimental fuel elements. Several experimental assemblies with mixed uranium-plutonium nitride fuel have been fabricated for tests in BOR-60 and BN-600. It is shown that the existing global experience in studying nitride fuel is insufficient for validating such fuel for use in BN-1200 and BREST. A complex program for computational-experimental validation of fuel elements is being implemented for validating the serviceability of fuel elements. © 2014, Springer Science+Business Media New York. Source


Vlaskin G.N.,Innovation and Technology Center for Proryv Project | Khomyakov Y.S.,Innovation and Technology Center for Proryv Project | Bulanenko V.I.,RAS Institute for Physics and Power Engineering
Atomic Energy | Year: 2015

Accurate data on the neutron yield from the interaction of α-particles with the nuclei of light elements ranging from lithium to potassium are required for solving the problems of nuclear power technologies: development of analytical means for controlling the technological processes of fabricating and reprocessing nuclear fuel, securing radiological protection for workers, improving the systems for managing and monitoring nuclear materials and radioactive wastes, measuring the burnup fraction of spent nuclear fuel, and others. The uncertainty of this information must be <10% for energies ranging from 4 to 9 MeV of α-particles emitted by naturally occurring and artificial radionuclides. The computational uncertainty of the neutron yield can be reduced on the basis of a combined analysis of (α, n) reactions, measured on α-particle accelerators with tunable energy and on compounds of actinides with light elements, using reliable data on the stopping power of α-particles for elements from hydrogen to californium. The results of such an analysis based on experimental and evaluated data for the light isotopes 6Li, 7Li, 9Be, 10B, 11B, 13C, 14N, 17O, 18O, 21Ne, 22Ne, 19F, 23Na, 25Mg, 26Mg, 27Al, 29Si, 30Si, 31P, 33S, 34S, 35Cl, 37Cl, and 41K in the α-particle energy range from 4 to 9 MeV are presented. © 2015, Springer Science+Business Media New York. Source


Troyanov V.M.,Innovation and Technology Center for Proryv Project | Grachev A.F.,Innovation and Technology Center for Proryv Project | Zabud'ko L.M.,Innovation and Technology Center for Proryv Project | Skupov M.V.,Russia Research Institute of Inorganic Materials | Kireev G.A.,Russia Research Institute of Inorganic Materials
Atomic Energy | Year: 2015

For future nuclear power with fast reactors with sodium (BN-1200) and lead (BREST) as coolants, plans are being made to use mixed uranium-plutonium nitride fuel as part of the Proryv project. A technology for carbothermal synthesis of mixed uranium-plutonium mononitride fuel and fabrication of pellets from it has now been developed. A program of comprehensive computational and experimental research on fuel to study the initial properties and their change under irradiation in reactor experiments is being implemented. Some results of pre-reactor studies of the properties of fuel and a program for future research are presented. © 2015, Springer Science+Business Media New York. Source

Discover hidden collaborations