A study of inter linkage effects on Candu feeder piping
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)
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)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43021665
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; CANADA; CANDU TYPE REACTORS; COMPUTER CODES; COOLANTS; DAMAGE; FINITE ELEMENT METHOD; FUEL CHANNELS; HEAT; HEAVY WATER; M CODES; PIPE FITTINGS; PIPES; REACTOR CORES; SIMULATION; STRESS ANALYSIS; STRESSES; THICKNESS; WALLS; WATER SUPPLY
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DEUTERIUM COMPOUNDS; DEVELOPED COUNTRIES; DIMENSIONS; ENERGY; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; MATHEMATICAL SOLUTIONS; NORTH AMERICA; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TUBES; WATER
Optional Information
- Notes
- 23 figs., 4 refs.