Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by M.G. Chasanov
Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.
Bibliography of Properties Data on Actinide Carbides and Nitrides
Transport Properties of Uranium Dioxide
Out-Of-Pile Study of the Effects of Thermal Gradients on the Distribution of Plutonium in Fast-Reactor Fuel Materials.
Related publications
Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core
Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.
Preparation of High Density Uranium Nitride and Uranium Carbonitride Fuel Pellets
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations.
Cs--U--O Phase Diagram and Its Application to Uranium--Plutonium Oxide Fast Reactor Fuel Pins
Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.
Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket
Nuclear Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Condensed Matter Physics
Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.
