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contributor authorJ. F. Unruh
contributor authorE. Z. Polch
contributor authorD. D. Kana
date accessioned2017-05-08T23:18:36Z
date available2017-05-08T23:18:36Z
date copyrightNovember, 1984
date issued1984
identifier issn0094-9930
identifier otherJPVTAS-28245#369_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/98858
description abstractRequalification of equipment in operating nuclear power plants to present-day criteria can be an expensive undertaking; however in situ measurements and data analysis procedures can be used to significantly reduce these costs. The procedures necessary to develop a required response spectrum for an instrument located at an elevated position within a base-fixed enclosure from modal analysis parameter measurements on the enclosure while installed in operating nuclear plant is addressed. Several examples are given to demonstate the ability of the procedures to develop the parameters necessary to predict component elevated responses from postulated enclosure base motion without recourse to analytical structural modeling of the base-fixed structure.
publisherThe American Society of Mechanical Engineers (ASME)
titleA Method for In Situ Test and Analysis of Nuclear Plant Equipment
typeJournal Paper
journal volume106
journal issue4
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.3264366
journal fristpage369
journal lastpage374
identifier eissn1528-8978
keywordsNuclear power stations
keywordsMeasurement
keywordsMotion
keywordsInstrumentation
keywordsModeling AND Spectra (Spectroscopy)
treeJournal of Pressure Vessel Technology:;1984:;volume( 106 ):;issue: 004
contenttypeFulltext


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