MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961

MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961 [electronic resource]

The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)

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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. Department of Energy, 1962.
Subjects:
Chemical Reactions.
Coolant Loops.
Fabrication.
Fuels.
Fused Salt Fuel.
In Pile Loops.
Irradiation.
Materials Testing.
Mechanical Structures.
Metallurgy.
Planning.
Reactor Core.
Power Plants.
Reprocessing.
Reactor Technology.

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Call Number: E 1.99:ornl-3215
E 1.99:ornl-3215 Available

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