Review of concrete properties for prestressed concrete pressure vesssels

Review of concrete properties for prestressed concrete pressure vesssels [electronic resource]

The desire for increasing power output along with safety requirements has resulted in consideration of the prestressed concrete pressure vessel (PCPV) for most current nuclear reactor systems, as well as for the very-high-temperature reactor for process heat and as primary pressure vessels for coal...

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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, 1976.
Subjects:
Design.
Mechanical Tests.
Materials.
Pressure Vessels.
Document Types.
Materials Testing.
Containers.
Concretes.
Building Materials.
Mechanical Properties.
Testing.
Radiation Effects.
Physical Radiation Effects.
Temperature Dependence.
Reviews.
Prestressed Concrete.
Materials Science.
General Studies Of Nuclear Reactors.

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Call Number: E 1.99:ornl/tm-5497
E 1.99:ornl/tm-5497 Available

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