Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels
- 1. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049 (China)
- 2. Atomic Energy of Canada Limited, Chalk River, Ont, K0J 1J0 (Canada)
Description
Highlights: → Two annular test sections were constructed with annular gaps of 4 and 6 mm. → Two heat transfer regions have been observed: normal and deteriorated heat transfer. → The spacer enhances the heat transfer at downstream locations. → The Jackson correlation agrees quite closely with the experimental data. - Abstract: An experiment has recently been completed at Xi'an Jiaotong University (XJTU) to obtain wall-temperature measurements at supercritical pressures with upward flow of water inside vertical annuli. Two annular test sections were constructed with annular gaps of 4 and 6 mm, respectively, and an internal heater of 8 mm outer diameter. Experimental-parameter ranges covered pressures of 23-28 MPa, mass fluxes of 350-1000 kg/m2/s, heat fluxes of 200-1000 kW/m2, and bulk inlet temperatures up to 400 deg. C. Depending on the flow conditions and heat fluxes, two distinctive heat transfer regimes, referring to as the normal heat transfer and deteriorated heat transfer, have been observed. At similar flow conditions, the heat transfer coefficients for the 6 mm gap annular channel are larger than those for the 4 mm gap annular channel. A strong effect of spiral spacer on heat transfer has been observed with a drastic reduction in wall temperature at locations downstream of the device in the annuli. Two tube-data-based correlations have been assessed against the experimental heat transfer results. The Jackson correlation agrees with the experimental trends and overpredicts slightly the heat transfer coefficients. The Dittus-Boelter correlation is applicable only for the normal heat transfer region but not for the deteriorated heat transfer region.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.07.007Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.07.007;
- PII
- S0029-5493(11)00544-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 241
- Journal Issue
- 9
- Journal Page Range
- p. 4045-4054
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 7. European Commission conference on Euratom research and training in reactor systems
- Acronym
- Fission Safety 2009
- Dates
- 22-24 Jun 2009
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43050180
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CORRELATIONS; EXPERIMENTAL DATA; HEAT FLUX; HEAT TRANSFER; HEATERS; MASS TRANSFER; PRESSURE RANGE MEGA PA; SPACERS; TEMPERATURE MEASUREMENT; TUBES; TURBULENT FLOW; WALLS; WATER
- Descriptors DEC
- DATA; ENERGY TRANSFER; FLUID FLOW; HYDROGEN COMPOUNDS; INFORMATION; NUMERICAL DATA; OXYGEN COMPOUNDS; PRESSURE RANGE
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.