Physics-based multiscale coupling for full core nuclear reactor simulation

Gaston, Derek R.; Permann, Cody J.; Peterson, John W.; Slaughter, Andrew E.; Andrš, David; Wang, Yaqi; Short, Michael P.; Perez, Danielle M.; Tonks, Michael R.; Ortensi, Javier; Zou, Ling; Martineau, Richard C.

doi:10.1016/j.anucene.2014.09.060

Title: Physics-based multiscale coupling for full core nuclear reactor simulation

Journal Article · Thu Oct 01 00:00:00 EDT 2015 · Annals of Nuclear Energy

DOI:https://doi.org/10.1016/j.anucene.2014.09.060· OSTI ID:1177665

Gaston, Derek R. ^[1]; Permann, Cody J. ^[1]; Peterson, John W. ^[1]; Slaughter, Andrew E. ^[1]; Andrš, David ^[1]; Wang, Yaqi ^[2]; Short, Michael P. ^[3]; Perez, Danielle M. ^[4]; Tonks, Michael R. ^[4]; Ortensi, Javier ^[2]; Zou, Ling ^[5]; Martineau, Richard C. ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States). Modeling and Simulation
Idaho National Lab. (INL), Idaho Falls, ID (United States). Reactor Physics Analysis and Design
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Dept. of Nuclear Science and Engineering
Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Modeling and Simulation
Idaho National Lab. (INL), Idaho Falls, ID (United States). Thermal Science and Safety Analysis

Numerical simulation of nuclear reactors is a key technology in the quest for improvements in efficiency, safety, and reliability of both existing and future reactor designs. Historically, simulation of an entire reactor was accomplished by linking together multiple existing codes that each simulated a subset of the relevant multiphysics phenomena. Recent advances in the MOOSE (Multiphysics Object Oriented Simulation Environment) framework have enabled a new approach: multiple domain-specific applications, all built on the same software framework, are efficiently linked to create a cohesive application. This is accomplished with a flexible coupling capability that allows for a variety of different data exchanges to occur simultaneously on high performance parallel computational hardware. Examples based on the KAIST-3A benchmark core, as well as a simplified Westinghouse AP-1000 configuration, demonstrate the power of this new framework for tackling—in a coupled, multiscale manner—crucial reactor phenomena such as CRUD-induced power shift and fuel shuffle. 2014 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-SA license

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Research Organization:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1177665

Report Number(s):: INL/JOU-14-33821; PII: S030645491400543X; TRN: US1500496

Journal Information:: Annals of Nuclear Energy, Vol. 84, Issue C; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 134 works

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Moltres: finite element based simulation of molten salt reactors Lindsay, Alexander; Huff, Kathryn The Journal of Open Source Software, Vol. 3, Issue 21 https://doi.org/10.21105/joss.00298	journal	January 2018
A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source Zabriskie, Adam; Schunert, Sebastian; Schwen, Daniel Nuclear Science and Engineering, Vol. 193, Issue 4 https://doi.org/10.1080/00295639.2018.1528802	journal	November 2018
Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review Matthews, Christopher; Unal, Cetin; Galloway, Jack Nuclear Technology, Vol. 198, Issue 3 https://doi.org/10.1080/00295450.2017.1323535	journal	June 2017
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