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contributor authorNima Zobeiry
contributor authorWolf Reinhardt
date accessioned2017-05-09T00:35:04Z
date available2017-05-09T00:35:04Z
date copyrightAugust, 2009
date issued2009
identifier issn0094-9930
identifier otherJPVTAS-28515#041802_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/141783
description abstractThe feeder pipes of a typical CANDU® reactor supply each of the 380 fuel channels with coolant and are individually connected to the large bore primary piping. In some designs, the longer pipes are interlinked with spacer rods, which mitigate vibrations and prevent contact between adjacent feeder pipes. Under severe loading conditions, the spacer rods will yield, which will prevent overstressing the pipes as the stiffness of the coupling gets reduced. Spacer yielding also provides increased damping for dynamic loads. It has recently become practicable to model the entire interlinked system in a single model. This paper presents the modeling approach for seismic analysis and for the fuel channel creep (a radiation induced slow unidirectional anchor motion). Results with and without spacer bars are compared to illustrate the effect of spacers. The importance of representing spacer yielding in the model is discussed.
publisherThe American Society of Mechanical Engineers (ASME)
titleA Modeling Approach for Interlinked Feeder Pipes in CANDU® Reactors
typeJournal Paper
journal volume131
journal issue4
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.3109985
journal fristpage41802
identifier eissn1528-8978
keywordsStress
keywordsModeling
keywordsPipes
keywordsCreep
keywordsChannels (Hydraulic engineering)
keywordsFuels AND Stiffness
treeJournal of Pressure Vessel Technology:;2009:;volume( 131 ):;issue: 004
contenttypeFulltext


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