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DNB type critical heat flux prediction in rod bundles with simplified grid spacer based on Liquid Sublayer Dryout model
- Source :
- Nuclear Engineering and Design. 351:94-105
- Publication Year :
- 2019
- Publisher :
- Elsevier BV, 2019.
-
Abstract
- Five published Liquid Sublayer Dryout (LSD) models are assessed using the Groeneveld Look-up table 2006 (LUT-2006) and critical heat flux (CHF) experimental data in circular tube under both subcooled boiling conditions and saturated boiling conditions. The flow regime transition from inverted annular flow to dispersed flow at post-CHF is postulated as the upper limit of the LSD model application range in saturated boiling region. Lee and Mudawar’s LSD model modified by W.X. Liu shows good agreement when void fractions is lower than 0.7. The modified L&M’s LSD model is coupled into subchannel code, COBRA-TF, to predict DNB type CHF in rod bundles. In present study, the gap clearance or thermal equivalent diameter of rod bundles is adopted as characteristic length in the modified L&M’s LSD model. For rod bundles with simplified grid spacers, Karman velocity distribution equation is utilized to calculate the velocity distribution normal to pin wall. The rod bundle CHF predictions by COBRA-TF coupled with LUT-2006, Bowring’s CHF correlation and the modified L&M’s LSD model, are compared with the CHF experimental data in 2 × 2 rod bundles with non-uniform power profile. Based on reasonable predictability on both the input power and axial position at CHF, the deviations of CHF predictions by the modified L&M’s LSD model, which adopts gap clearance instead of thermal equivalent diameter as characteristic length, and Bowring’s CHF correlation are within ±20% as void fraction approaching to 0.7.
- Subjects :
- Nuclear and High Energy Physics
Materials science
Characteristic length
Critical heat flux
020209 energy
Mechanical Engineering
02 engineering and technology
Mechanics
01 natural sciences
010305 fluids & plasmas
Subcooling
Nuclear Energy and Engineering
Bundle
Boiling
0103 physical sciences
Thermal
0202 electrical engineering, electronic engineering, information engineering
General Materials Science
Hydraulic diameter
Safety, Risk, Reliability and Quality
Porosity
Waste Management and Disposal
Subjects
Details
- ISSN :
- 00295493
- Volume :
- 351
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design
- Accession number :
- edsair.doi...........fdf8a920d93d0e3e234f223b35de7748