Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.

doi 10.2172/4831462
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Office of Scientific and Technical Information (OSTI)

Related search

Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core

2014English

Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
2011English

Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.

1970English

Preparation of High Density Uranium Nitride and Uranium Carbonitride Fuel Pellets

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1972English

Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations.

1968English

Cs--U--O Phase Diagram and Its Application to Uranium--Plutonium Oxide Fast Reactor Fuel Pins

1977English

Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.

2006English

Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket

Nuclear Technology
High Energy PhysicsNuclearEngineeringNuclear EnergyCondensed Matter Physics
2010English

Use of Neutron Filters for Fast Reactor Fuel Irradiations in a Thermal Reactor Core.

1966English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy