Abstract
The turbulent mixing modeling for unsteady heat transfer problems in thermal-hydraulics has long been a focus in nuclear engineering community. One of the promising approaches that takes a full advantage of recent advances in HPC is the use of hierarchy of fidelity simulations that are cross-verified and validated in the regimes of interest. In particular, it is beneficial to have a higher fidelity reference simulation that could be used for benchmarking of the faster-turn-around lower-fidelity tools. This paper focuses on Nek5000 LES reference simulations for the OECD/NEA T-junction and Matis benchmarks and for the "SIBERIA" and MAX con-current validation experiments. The CFD capabilities to predict the unsteady heat transfer problems that are associated with non- isothermal flow mixing in pipe flows and related to thermal fatigue of nuclear power plant pipe system have been tested in the 2010 Vattenfall T-junction benchmark. The 2012 KAERI Matis experiment has tested the CFD predictions in a complex geometry of subchannel mixing flow behind a spacer grid. The Nek5000 LES submissions scored highly in the both blind benchmarks. The Novosibirsk's "SIBERIA" experiment employs a novel electrochemical technique for accurate measurement of the wall mean shear and its fluctuations in an annular channel flow with a blockage. The ANL's MAX experiment is designed to study thermal mixing in a wide mixing chamber where two out of a maximum of four adjacent differentially heated jets are injected to impinge on the top wall surface, leading to a thermal striping phenomenon. The resulting complex flow configuration is tracked by a high-resolution particle velocimetry method and thermal imaging. The high-quality benchmark data profiles and high-resolution MAX data provided are used for validating numerical simulation capabilities of Nek5000 for these types of flows and for benchmarking and improvement of lower-fidelity uRANS modeling as a part of hierarchical multi-fidelity approach.
Original language | English |
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Title of host publication | International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 |
Publisher | American Nuclear Society |
Pages | 1462-1473 |
Number of pages | 12 |
ISBN (Electronic) | 9781510811843 |
State | Published - 2015 |
Event | 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States Duration: Aug 30 2015 → Sep 4 2015 |
Publication series
Name | International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 |
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Volume | 2 |
Conference
Conference | 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 |
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Country/Territory | United States |
City | Chicago |
Period | 08/30/15 → 09/4/15 |
Bibliographical note
Publisher Copyright:© Copyright (2015) by American Nuclear Society All rights reserved.
Keywords
- CFD
- LES
- Spacer grid
- Thermal striping
- Turbulent mixing