Numerical study of heat transfer in a distorted rod bundle
- 1. Heat, Flow and Turbulence Research Group, Department of Mechanical Engineering, The University of Sheffield, S1 3JD (United Kingdom)
- 2. Fuel Route Systems Branch, Engineering, EDF Energy Generation, Barnett Way, Barnwood, Gloucester GL4 3RS (United Kingdom)
Description
Highlights: • Strong cross flows evidenced in the distorted bundle result in the formation of large swirling flow structures. • The peak fuel pin temperature does not coincide with the location of worst distortion for the damaged bundle. • The subchannel bulk temperature varies non-monotonically in the vertical direction. - Abstract: The effect of rod distortion on the flow and heat transfer in a rod (fuel) bundle similar to those in an Advanced Gas-cooled Reactor (AGR) is investigated using carefully constructed CFD models. The results are of relevance to various other engineering applications, for example heat exchangers. The distorted element contracts gradually over the first half of the element, reaching a minimum at half high then subsequently increasing back to its normal value over the second half of the element. In this paper, the results for forced convection are presented. Changes in the rod profiles divert flow to regions of less resistance, resulting in strong cross flow recirculation regions. The resultant three dimensional flow is also accompanied by large scale swirling flow around the fuel pins. The hotspot at any height coincides with the leeward side of the cross flow. It is rather surprising that the peak can temperature at the location of worst bundle distortion (i.e middle height) is actually slightly lower than that of intact fuel. The overall peak can temperature in the damaged bundle is however much higher than that in the intact fuel, and this occurs towards the top of the bundle.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2019.04.003Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2019.04.003;
- PII
- S002954931830997X;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 349
- Journal Page Range
- p. 63-77
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51056385
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- FORCED CONVECTION; FUEL ELEMENT CLUSTERS; FUEL PINS; FUEL RODS; GAS COOLED REACTORS; HEAT EXCHANGERS; NUMERICAL ANALYSIS; PEAKS; TEMPERATURE MONITORING; THREE-DIMENSIONAL CALCULATIONS; VORTEX FLOW
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENTS; HEAT TRANSFER; MASS TRANSFER; MATHEMATICS; MONITORING; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- © 2019 Elsevier B.V. All rights reserved.