Development of a pneumatic transfer system for HTGR recycle fuel particles

Development of a pneumatic transfer system for HTGR recycle fuel particles [electronic resource]

In support of the High-Temperature Gas-Cooled Reactor (HTGR) Fuel Refabrication Development Program, an experimental pneumatic transfer system was constructed to determine the feasibility of pneumatically conveying pyrocarbon-coated fuel particles of Triso and Biso designs. Tests were conducted with...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge, Tenn. : Oak Ridge National Laboratory. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1978.
Subjects:
Wear.
Uranium Compounds.
Velocity.
Carbides.
Graphite Moderated Reactors.
Coated Fuel Particles.
Fuel Cycle.
Actinide Compounds.
Oxygen Compounds.
Carbon Compounds.
Uranium Dioxide.
Elements.
Uranium Carbides.
Htgr Type Reactors.
Remote Handling.
Pyrolytic Carbon.
Fuel Particles.
Carbon.
Pneumatic Transport.
Nonmetals.
Reactors.
Uranium Oxides.
Silicon Compounds.
Transport.
Pressure Drop.
Oxides.
Silicon Carbides.
Gas Cooled Reactors.
Chalcogenides.
Nuclear Fuel Cycle And Fuel Materials.
Materials Science.
Specific Nuclear Reactors And Associated Plants.

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Call Number: E 1.99:ornl/tm-6169
E 1.99:ornl/tm-6169 Available

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