@inproceedings{93d6dc1dba8c4aa5b7e6ac127e99476b,
title = "Multiscale core thermal-hydraulics analysis of the pebble bed fluoride-salt-cooled high-temperature reactor (Pb-FHR)",
abstract = "The complex core geometry of Pebble Bed Reactors (PBRs) necessitates multiscale techniques for accurate prediction of temperature and flow distributions. This paper presents the multiscale Thermal-Hydraulic (T/H) models used in the Pronghorn PBR simulation tool with application to the Mark-1 Pebble Bed Fluoride-Salt Cooled High-Temperature Reactor (PB-FHR). Pronghorn{\textquoteright}s multiscale model is compared against a simpler model recently used for analysis of Doppler-driven transients in the PB-FHR. Comparisons with explicitly-meshed pebbles show that Pronghorn can predict material-wise maximum and average temperatures to less than 10°C over a wide range of thermal conditions, while the simpler model is characterized by errors of 40 to 200°C. Steady-state analysis of the PB-FHR demonstrates Pronghorn{\textquoteright}s capabilities as a multiscale T/H solver for PBRs.",
author = "Novak, {A. J.} and Slaybaugh, {R. N.} and Martineau, {R. C.}",
note = "Publisher Copyright: {\textcopyright} 2019 American Nuclear Society. All rights reserved.; 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 ; Conference date: 25-08-2019 Through 29-08-2019",
year = "2019",
language = "English (US)",
series = "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019",
publisher = "American Nuclear Society",
pages = "397--410",
booktitle = "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019",
address = "United States",
}