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

QUARTERLY PROGRESS REPORT FOR THE PERIOD OCTOBER 1 TO DECEMBER 31, 1958

Technical Report ·
OSTI ID:4249806
A technical description is givcn of the research and development work accomplished and the progress made in the Yankee Reactor Program. New methods were developed for measuring and speciiying pellet densities, which will enable substantial cost reductions to be made. A uniformly enriched first core was selected in preference to a two-region or two-enrichment core, as a result of a comprehensive study of various loading configurations. Dynamic autoclave corrosion tests of primary system materials to determine the effect of concentration cycling of boric acid in high temperature pressurized water and the comparative effect of low lithium hydroxide indicated generally low corrosion rates. The results of analytical and experimental thermal defiection studies led to the selection of the compromise fuel assembly design for the first core. Excellent performance was obtained from manual and automatic operation of a prototype of the positive engagement latch-type magnetic jack control rod drive mechanism. A triple taper hydraulic shock absorber was designed for use with the first core control rods, on the basis of data obtained from repetitive hydraulic tests. Additional modifications were made to the WCAP-4 in-pile test loop sampling systems in order to conduct final acccptance tests. Detailed information was obtained on the post-irradiation examinations performed on process water samples WCAP-1-4 and 2-3. The appendix contains the latest nuclear, mechanicals and thermal design data for the first core. (For preceding period see YAEC-97.) (auth)
Research Organization:
Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
NSA Number:
NSA-13-014098
OSTI ID:
4249806
Report Number(s):
YAEC-113
Country of Publication:
United States
Language:
English