AbstractAbstract
No abstract available
Original Title
PWR reactors
Primary Subject
Source
Mar 1974; 67 p; USAEC Tech. Info. Center.
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Report
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AbstractAbstract
[en] It is shown that 1/24th scale model test results accurately predict the flow-induced vibration and modes of full-size reactor internals. Dimensional analysis principles are reviewed and the similitude requirements for valid model tests of the flow-induced vibration of reactor internals are identified. Test results on reactor internals flow vibration models are presented and compared with plant test results. Reactor internals with neutron pads are shown to vibrate only about one-third as much as internals having a thermal shield. 17 references
Original Title
PWR
Primary Subject
Source
Jul 1975; 73 p; PWR Systems Div., Pittsburgh, PA.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue