Actions for Assessment of the consequences of boiling in the radial blanket due to hypothetical major pipe leaks

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Assessment of the consequences of boiling in the radial blanket due to hypothetical major pipe leaks

Author
Prasad, K. N.
Published
United States : [publisher not identified], 1977.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1977.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Tilbrook, R. W.

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Summary
The orificing arrangement in CRBRP permits the possibility of limited boiling in the radial blanket for certain hypothetical transients that would not result in boiling in the core. Limited boiling in the radial blanket may result in acceptable consequences because of the steep power and temperature profiles which offer a high potential for condensation of the limited amount of vapor formed. The analysis presented indicates that the coolant in the highest power radial blanket assemblies may exceed saturation temperature in no more than six subchannels for a hypothetical major leak, even applying hot channel factors to all pins. The void thus formed is unlikely to expand across the cross section of the assembly because cooler sodium and pins in the vicinity could act as temporary heat sinks and cause the vapor to condense. The void is likely to collapse before dryout occurs. Even if dryout is postulated, melting of the clad could only occur on a long time scale compared to expected flow recovery times.
Report Numbers
CONF-770611-15
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: EY-76-C-15-2395
OSTI Identifier 7211731
Research organization: Westinghouse Electric Corp., Madison, PA (USA).
View MARC record | catkey: 44260934