TY - JOUR
T1 - Pronghorn
T2 - 2018 Transactions of the American Nuclear Society, ANS 2018
AU - Novak, April J.
AU - Zou, Ling
AU - Peterson, John W.
AU - Martineau, Richard C.
AU - Slaybaugh, Rachel N.
N1 - Funding Information:
This material is based upon work supported by a Department of Energy Nuclear Energy University Programs Graduate Fellowship.
Publisher Copyright:
© 2018 American Nuclear Society. All rights reserved.
PY - 2018
Y1 - 2018
N2 - Pebble bed High Temperature Reactors (HTRs) are characterized by many advantageous design features, such as excellent passive heat removal in accidents and large margins to fuel failure. However, a significant challenge in thermal-hydraulic core modeling of pebble bed reactors is the double heterogeneity random packing of hundreds of thousands of fuel pebbles and thousands of fuel particles per pebble. A new porous media thermal-hydraulics code, Pronghorn, is under development to provide a fast-running, medium-fidelity core simulator and serve as a bridge between low-resolution system level codes and high-resolution Computational Fluid Dynamics (CFD) codes for multiscale analysis. Pronghorn is based on the Mul-tiphysics Object-Oriented Simulation Environment (MOOSE) finite element framework, and permits an arbitrary equation of state, unstructured mesh capabilities, modern software design, and the ability to couple to MOOSE fuels performance and systems-level Thermal-Hydraulic (T/H) codes. To address the wide variety in gas- and liquid-cooled pebble bed reactor designs, Pronghorn includes several different flow models, each most appropriate to a range of compressibilities and operating conditions. This paper reviews benchmarking efforts of a low-advection flow model appropriate for Loss of Forced Circulation (LOFC) simulations and introduces the new fully compressible flow model with preliminary validation by comparison to potential flow theory for low Mach number flow over a cylinder.
AB - Pebble bed High Temperature Reactors (HTRs) are characterized by many advantageous design features, such as excellent passive heat removal in accidents and large margins to fuel failure. However, a significant challenge in thermal-hydraulic core modeling of pebble bed reactors is the double heterogeneity random packing of hundreds of thousands of fuel pebbles and thousands of fuel particles per pebble. A new porous media thermal-hydraulics code, Pronghorn, is under development to provide a fast-running, medium-fidelity core simulator and serve as a bridge between low-resolution system level codes and high-resolution Computational Fluid Dynamics (CFD) codes for multiscale analysis. Pronghorn is based on the Mul-tiphysics Object-Oriented Simulation Environment (MOOSE) finite element framework, and permits an arbitrary equation of state, unstructured mesh capabilities, modern software design, and the ability to couple to MOOSE fuels performance and systems-level Thermal-Hydraulic (T/H) codes. To address the wide variety in gas- and liquid-cooled pebble bed reactor designs, Pronghorn includes several different flow models, each most appropriate to a range of compressibilities and operating conditions. This paper reviews benchmarking efforts of a low-advection flow model appropriate for Loss of Forced Circulation (LOFC) simulations and introduces the new fully compressible flow model with preliminary validation by comparison to potential flow theory for low Mach number flow over a cylinder.
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M3 - Conference article
AN - SCOPUS:85060868985
SN - 0003-018X
VL - 119
SP - 175
EP - 178
JO - Transactions of the American Nuclear Society
JF - Transactions of the American Nuclear Society
Y2 - 11 November 2018 through 15 November 2018
ER -