@inproceedings{689c4dd164ca46a1b874931e17db569b,
title = "NEAMS IRP Challenge Problem 1: Flexible Modeling for Heat Transfer for Applications in Advanced Reactors",
abstract = "The adoption of liquid metals and molten salts as coolant fluids in advanced reactor designs has challenged traditional turbulence and heat transfer models because of vastly different heat transfer characteristics from water. The challenge is exacerbated by the yet-to-be-understood mixed convection regime, which is crucial to passive heat removal. The NEAMS IRP Challenge Problem 1 (CP1) aims to facilitate scale-flexible heat transfer models that can serve for broader applications in reactor thermal-hydraulic analysis. CP1 research activities include direct numerical simulation (DNS) and the development of advanced turbulence modeling techniques. The DNS efforts studies the low- and high-Prandtl mixed convection in the identified canonical flow scenario, from which the fundamental understanding on the effect of buoyancy on turbulence and heat transfer is investigated. The CP1 modeling endeavors aim at advancement of the present engineering models and the employment of the data driven (DD) methods for the turbulence modeling. In the engineering model concentration, the performance of the current CFD models is assessed in the non-unitary Prandtl flows to gain physical understanding of their shortcomings. A framework for model form error prediction and error propagation estimation is also established. A DD RANS framework is developed for the frozen prediction of Reynolds stress and turbulent heat flux based on the polynomial tensor representation of the respective quantities. The DD framework showed satisfactory performance over the k − τ model in the forced and mixed convection cases.",
author = "Bolotnov, {Igor A.} and Iskhakov, {Arsen S.} and Tri Nguyen and Tai, {Cheng Kai} and Ralph Wiser and Emilio Baglietto and Nam Dinh and Dillon Shaver and Elia Merzari",
note = "Publisher Copyright: {\textcopyright} 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.; 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 ; Conference date: 20-08-2023 Through 25-08-2023",
year = "2023",
doi = "10.13182/NURETH20-40393",
language = "English (US)",
series = "Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023",
publisher = "American Nuclear Society",
pages = "4450--4463",
booktitle = "Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023",
address = "United States",
}