Abstract
The critical heat flux (CHF) corresponding to the departure from nucleate boiling (DNB) is one of the major limiting factors in the design and operation of pressurized water reactors (PWRs). Various predictive tools have been proposed for steady-state conditions. Empirical correlations and look-up tables yield relatively good agreement with specific experimental datasets and are widely used in subchannel codes for PWR transient simulations. However, experimental studies have revealed that during fast transients the CHF values can become significantly higher than those in steady-state or slow transient scenarios, causing this modeling approach to result in overly conservative DNB prediction. This paper presents a mechanistic transient CHF model. Based on prior work, two DNB triggering mechanisms prevail in this model-The hydrodynamic thinning process and the thermal thinning process-both of which rely on the liquid sublayer dryout theory. Both mechanisms evaluate the depletion of the liquid sublayer underneath vapor slugs flowing over the channel. This model is further validated against three sets of power transient experiments at different operating conditions. While it clearly outperforms steady-state approaches and generally agrees closely with measurements, it still remarkably under-estimates CHF for very fast transients at low pressure. Future investigations will address this limitation.
Original language | English |
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Title of host publication | Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 |
Publisher | American Nuclear Society |
Pages | 148-155 |
Number of pages | 8 |
ISBN (Electronic) | 9780894487552 |
State | Published - 2018 |
Event | 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 - Charlotte, United States Duration: Apr 8 2018 → Apr 11 2018 |
Publication series
Name | Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 |
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Conference
Conference | 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 |
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Country/Territory | United States |
City | Charlotte |
Period | 04/8/18 → 04/11/18 |
Funding
Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan. This research project is supported by the Consortium for Advanced Simulation of Light Water Reactors (CASL), an Energy Innovation Hub for modeling and simulation of nuclear reactors under the U.S. Department of Energy.