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MODEL STUDIES OF REACTOR COOLANT AND FUEL PIN BEHAVIOR UNDER CONDITIONS OF COOLANT BOILING AND OVERHEATING OF THE FUEL ELEMENTS. Engineering Research Department Report 59D65

Author
Smith, J. O.
Published
United States : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961.
Physical Description
microfiche : negative ; 8 x 13 cm
Additional Creators
Kaercher, G. C. and Shuttleworth, C. J.

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Summary
Studies were made to obtain experimentai data by which the behavior of the coolant and fuel elements of the Enrico Fermi Reactor can be predicted under conditions beyond those of normal operation. A model test section was constructed that simulated the passages for coolant flow through partial cross sections of a reactor core subassembly, upper blanket subassembly, and lower blanket subassembly with inlet nozzle. The model core section was 1 cm square in cross section and contained 4 dummy fuel pins, which were electrically heated. The blanket models were round tubes of such proportions that the percentage of the total pressure drop through each of the sections was approximately equal to the pressure drop percertage in the corresponding reactor component. The test section was incorporated in a vertically oriented test loop in which water at reduced pressure was circulated as coolant. Results of tests on two-phase flow, liquid expulsion, natural circulation, and meltdown are presented. (M.C.G.)
Report Numbers
TID-18229
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(11-1)-865
NSA number: NSA-17-017556
OSTI Identifier 4739999
Research organization: Detroit Edison Co., Detroit.
View MARC record | catkey: 42251094