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Analysis of Water Hammer due to Sudden Rupture of Reactor Coolant System

[+] Author Affiliations
Iaroslav Dubyk, Igor Orynyak

“IPP-CENTRE” LTD, Kiev, Ukraine

Paper No. PVP2016-63589, pp. V004T04A021; 9 pages
  • ASME 2016 Pressure Vessels and Piping Conference
  • Volume 4: Fluid-Structure Interaction
  • Vancouver, British Columbia, Canada, July 17–21, 2016
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 978-0-7918-5040-4
  • Copyright © 2016 by ASME


In this article we have analyzed the most severe design accident for the reactor facility — sudden rupture of the primary cooling loop. This rupture causes a water hammer event for the reactor core barrel, which is a significant but short term load. Assuming that core barrel is a thin shell, we have performed dynamic stress and strain calculations in the frequency domain. The Duhamel integral was used to calculate the transient response of a shell to an impulse load caused by the water hammer event. The results obtained were used to estimate structural stability of the core barrel.

Copyright © 2016 by ASME



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