CFD simulation of vertical seven-rod bundle cooled with supercritical Freon-12
Creators
- 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
Description
In this paper, a seven-rod bare bundle was simulated using ANSYS Fluent 6.3.26 to accurately predict the fluid flow and heat transfer behaviour under supercritical flow conditions. Seven turbulence models were compared to identify the appropriate model to predict the experiments performed at the Institute of Physics and Power Engineering on a vertically oriented seven-rod bare bundle cooled with supercritical Freon-12. It was found that predictions of wall temperatures and heat transfer coefficients are sensitive to the choice of turbulence model as well as to the near-wall treatment. Overall, the CFD simulations were able to predict the measured sheath temperature profiles along the length of the bundle within reasonable accuracy. (author)
Availability note (English)
Available from http:dx.doi.org/10.12943/ANR.2014.00028Additional details
Identifiers
Publishing Information
- Journal Title
- AECL Nuclear Review (Online)
- Journal Volume
- 3
- Journal Issue
- 1
- Journal Page Range
- p. 17-28
- ISSN
- 1929-6371
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 45091522
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; FLUID FLOW; FREONS; FUEL ELEMENT CLUSTERS; HEAT TRANSFER; TURBULENT FLOW
- Descriptors DEC
- ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; HALOGENATED ALIPHATIC HYDROCARBONS; HEAVY WATER MODERATED REACTORS; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- 13 refs., 5 tabs., 10 figs.