Published July 2005 | Version v1
Book

A study of inter linkage effects on Candu feeder piping

  • 1. Ontario Power Generation Inc., Ontario (Canada)

Description

A CANDU (Canadian Deuterium Uranium) reactor core consists of a large number of fuel channels where heat is generated. Two feeder pipes are connected to each fuel channel to transport D2O coolant into and out of the reactor core. The feeder piping is designed to the requirements of Class 1 piping of Section III NB of the ASME Boiler and Pressure Vessel and CSA Codes. Feeder piping stress analysis is being performed to demonstrate the code compliance check and the fitness for service of feeders. In the past, stress analyses were conducted for each individual feeder without including interaction effects among connected feeders. Interaction effects occur as a result of linkages that exist between feeders to prevent fretting and impacting damage during normal, abnormal and accident conditions. In this paper, a 'combined' approach is adopted to include all feeders connected by inter linkages into one feeder piping model. MSC/NASTRAN finite element software was used in the stress simulation, which contains up to 127 feeder pipes. The ASME Class 1 piping analysis was conducted to investigate the effects of the linkages between feeders. Both seismic time history and broadened response spectra methods were used in the seismic stress calculation. The results show that the effect of linkages is significant in dynamic stresses for all feeder configurations, as well as in static stresses for certain feeder configurations. The single feeder analysis could either underestimate or overestimate feeder stresses depending on the pipe geometry and bend wall thickness. (authors)

Part of:
Proceedings of 18th international conference on structural mechanics in reactor technology

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-3421-7
Imprint Title
Proceedings of 18th international conference on structural mechanics in reactor technology
Imprint Pagination
4896 p.
Journal Page Range
p. 3613-3627

Conference

Title
18. international conference on structural mechanics in reactor technology
Dates
7-12 Aug 2005
Place
Beijing (China)

Optional Information

Notes
23 figs., 4 refs.