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Moore, S.E.; Bryson, J.W.
Annual report of contract research for the Metallurgy and Materials Research Branch, Division of Reactor Safety Research, fiscal year 19761977
Annual report of contract research for the Metallurgy and Materials Research Branch, Division of Reactor Safety Research, fiscal year 19761977
AbstractAbstract
[en] This report reviews the activities and accomplishments of the Design Criteria for Piping and Nozzles program being conducted by the Oak Ridge National Laboratory for the period July 1, 1975, to September 30, 1976. The objectives of the program are to conduct integrated experimental and analytical stress analysis studies of piping system components and isolated and closely-spaced pressure vessel nozzles in order to confirm and/or improve the adequacy of structural design criteria and analytical methods used to assure the safe design of nuclear power plants. Activities this year included the development of a finite-element program for analyzing two closely spaced nozzles in a cylindrical pressure vessel; a limited-parameter study of vessels with isolated nozzles, finite-element studies of piping elbows, a fatigue test of an out-of-round elbow, summary and evaluation of experimental studies on the elastic-response and fatigue failure of tees, parameter studies on the behavior of flanged joints, publication of fifteen topical reports and papers on various experimental and analytical studies; and the development and acceptance of a number of design rules changes to the ASME Code. 2 figures, 2 tables
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Source
Nuclear Regulatory Commission, Washington, D.C. (USA). Office of Nuclear Regulatory Research; p. 90-107; Jan 1977; p. 90-107
Record Type
Report
Literature Type
Progress Report
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