The 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.
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August 2009
Research Papers
A Modeling Approach for Interlinked Feeder Pipes in CANDU® Reactors
Nima Zobeiry,
Nima Zobeiry
Atomic Energy of Canada Limited
, Mississauga, ON, L5K1B2, Canada
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Wolf Reinhardt
Wolf Reinhardt
Atomic Energy of Canada Limited
, Mississauga, ON, L5K1B2, Canada
Search for other works by this author on:
Nima Zobeiry
Atomic Energy of Canada Limited
, Mississauga, ON, L5K1B2, Canada
Wolf Reinhardt
Atomic Energy of Canada Limited
, Mississauga, ON, L5K1B2, CanadaJ. Pressure Vessel Technol. Aug 2009, 131(4): 041802 (6 pages)
Published Online: June 26, 2009
Article history
Received:
December 14, 2007
Revised:
August 13, 2008
Published:
June 26, 2009
Citation
Zobeiry, N., and Reinhardt, W. (June 26, 2009). "A Modeling Approach for Interlinked Feeder Pipes in CANDU® Reactors." ASME. J. Pressure Vessel Technol. August 2009; 131(4): 041802. https://doi.org/10.1115/1.3109985
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