The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels
Creators
- 1. Canadian Nuclear Safety Commission, Ottawa, Ontario K1P 5S9 (Canada)
- 2. Canadian Nuclear Laboratories (CNL), Chalk River, Ont. K0J 1J0 (Canada)
Description
Highlights: • Presentation of the "advanced" drift-flux model of the subchannel code ASSERT-PV. • Study the effect of the drift-flux model of ASSERT on CHF and flow distribution. • Quantify model component effects with flow, quality and dryout power measurements. - Abstract: This paper studies the effect of the drift flux model of the subchannel code ASSERT-PV on critical heat flux (CHF), void fraction and flow distribution across fuel bundles. Numerical experiments and comparison against measurements were performed to examine the trends and relative behaviour of the different components of the model under various flow conditions. The drift flux model of ASSERT-PV is composed of three components: (a) the lateral component or diversion cross-flow, caused by pressure difference between connected subchannels, (b) the turbulent diffusion component or the turbulent mixing through gaps of subchannels, caused by instantaneous turbulent fluctuations or flow oscillations, and (c) the void drift component that occurs due to the two-phase tendency toward a preferred distribution. This study shows that the drift flux model has a significant impact on CHF, void fraction and flow distribution predictions. The lateral component of the drift flux model has a stronger effect on CHF predictions than the axial component, especially for horizontal flow. Predictions of CHF, void fraction and flow distributions are most sensitive to the turbulent diffusion component of the model, followed by the void drift component. Buoyancy drift can be significant, but it does not have as much influence on CHF and flow distribution as the turbulent diffusion and void drift.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.02.021Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.02.021;
- PII
- S0306-4549(16)30671-5;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 104
- Journal Page Range
- p. 197-213
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48086655
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; CANDU TYPE REACTORS; COMPARATIVE EVALUATIONS; CRITICAL HEAT FLUX; DIFFUSION; DRYOUT; FLUCTUATIONS; FUEL ELEMENT CLUSTERS; VOID FRACTION
- Descriptors DEC
- COMPUTER CODES; EVALUATION; FUEL ASSEMBLIES; HEAT FLUX; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; VARIATIONS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.