70-MWt LMFBR steam generator test facility

Author: Johanson, J. G.
Published: United States : American Society of Mechanical Engineers,New York, 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description: microfiche : negative ; 11 x 15 cm
Additional Creators: Gimera, R. J.

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Summary

The existing 35-MWt Sodium Components Test Installation (SCTI) is being upgraded to 70 MWt. The first test article in the upgraded facility will be the Clinch River Breeder Reactor (CRBR) prototype steam generator. The paper describes the upgraded facility design and test capabilities, the CRBR steam generator major design features, the test program for the steam generator, and the current status of design and construction of the facility.

Report Numbers

CONF-760944-1

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: E(04-3)-0700
OSTI Identifier 7325397

View MARC record | catkey: 43929749