GAS-COOLED REACTOR AND THORIUM UTILIZATION PROGRAMS. Semiannual Progress Report for Period Ending September 30, 1970

GAS-COOLED REACTOR AND THORIUM UTILIZATION PROGRAMS. Semiannual Progress Report for Period Ending September 30, 1970 [electronic resource]

Reactors, Gas-Cooled/Fuel Cycles For High Temperature, Development Of Thorium--Uranium-233; Reactor Fuels/Radiation Effects Testing Of Thorium Oxide (Tho$Sub 2$)--Uranium Oxide (Uo$Sub 2$) Coated Particle; Reactor Fuels/Fission Product Release From Irradiated Coated Particle, Effects Of Annealing On...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : U.S. Atomic Energy Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1971.
Subjects:
Annealing.
Breeder Reactors.
Cesium.
Chemical Reactions.
Coated Fuel Particles.
Coolant Loops.
Corrosion.
Fabrication.
Failures.
Fast Reactors.
Fission Products.
Fuel Cycle.
Fuel Elements.
Fuels.
Graphite.
Htgr Type Reactors.
Irradiation.
Mass Transfer.
Mockup.
Plutonium Oxides.
Preparation.
Pressure Vessels.
Prestressed Concrete.
Radiation Effects.
Reprocessing.
Steam.
Steam Generators.
Thorium Oxides.
Uranium Dioxide.
Welds.
N38150* > Power Reactor Development > Fuels.
N30250 > Metals, Ceramics, & Other Materials > Ceramics & Cermets > Radiation Effects.
N30330 > Metals, Ceramics, & Other Materials > Plastics & Other Materials > Properties Evaluations.
N20510 > Chemistry > Radiochemistry & Nuclear Chemistry > Reactor Fuel Processing.

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