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U.S. Department of Energy
Office of Scientific and Technical Information

QUARTERLY PROGRESS REPORT FOR THE PERIOD OCTOBER 1, 1957 TO DECEMBER 31, 1957

Technical Report ·
OSTI ID:4308416
An evaluation and the resulting conclusions of work performed are presented for each project in which definitive progress was made. The principle progress consisted of: improvement in the uniformity of spacing pellets in stainless steel tubes by horizontal and vertical stretching of the tubes; determination of bulk-boiling factors from the loss-of-coolant flow studies; the obtaining of encouraging results from the use of a basic permanganate-citrate method for the decontamination of stainless steel; calculation of the volume of the local boiling in the first core; selection of a combination resin-evaporation waste disposal system; review and modification of nuclear parameters and control rod worths; loading of the CRX core to criticality and the obtaining of test data from the loading operations; preparation of drawings and equipment specifications for the in-pile test loop in a fourteen-section package; and removal of irradiated fuel elements test specimens from the MTR and their shipment to KAFL for postirradiation examination. The latest revised definitive mechanical, thermal, and nuclear design data for the first Yankee core are included. (For preceding period see YAEC-44.) (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
NSA Number:
NSA-12-016726
OSTI ID:
4308416
Report Number(s):
YAEC-52
Country of Publication:
United States
Language:
English