A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS

A simulation suite has been developed to model reactor power distribution and multiphysics feedback effects in Sodium-cooled Fast Reactors (SFRs). This suite is based on the Finite Element Method (FEM) and employs a general, unstructured mesh to solve the Simplified P3 (SP3) neutron transport equati...

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Main Authors: Dawn William C., Palmtag Scott
Format: Article
Language:English
Published: EDP Sciences 2021-01-01
Series:EPJ Web of Conferences
Subjects:
Online Access:https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06019.pdf
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spelling doaj-458a89d92a964178865f7727e91bf4712021-08-02T16:00:51ZengEDP SciencesEPJ Web of Conferences2100-014X2021-01-012470601910.1051/epjconf/202124706019epjconf_physor2020_06019A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORSDawn William C.0Palmtag Scott1Department of Nuclear Engineering, North Carolina State University RaleighDepartment of Nuclear Engineering, North Carolina State University RaleighA simulation suite has been developed to model reactor power distribution and multiphysics feedback effects in Sodium-cooled Fast Reactors (SFRs). This suite is based on the Finite Element Method (FEM) and employs a general, unstructured mesh to solve the Simplified P3 (SP3) neutron transport equations. In the FEM implementation, two-dimensional triangular elements and three-dimensional wedge elements are selected. Wedge elements are selected for their natural description of hexagonal geometry common to fast reactors. Thermal feedback effects within fast reactors are modeled within the simulation suite. A thermal hydraulic model is developed, modeling both axial heat convection and radial heat conduction within fuel assemblies. A thermal expansion model is included and is demonstrated to significantly affect reactivity. This simulation suite has been employed to model the Advanced Burner Reactor (ABR) benchmark, specifically the MET-1000. It has been demonstrated that these models sufficiently describe the multiphysics feedback phenomena and can be used to estimate multiphysics reactivity feedback coefficients.https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06019.pdfsodium-cooled fast reactor (sfr)simplified pn (spn)finite element method (fem)thermal hydraulicsthermal expansionmultiphysics
collection DOAJ
language English
format Article
sources DOAJ
author Dawn William C.
Palmtag Scott
spellingShingle Dawn William C.
Palmtag Scott
A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
EPJ Web of Conferences
sodium-cooled fast reactor (sfr)
simplified pn (spn)
finite element method (fem)
thermal hydraulics
thermal expansion
multiphysics
author_facet Dawn William C.
Palmtag Scott
author_sort Dawn William C.
title A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
title_short A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
title_full A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
title_fullStr A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
title_full_unstemmed A MULTIPHYSICS SIMULATION SUITE FOR SODIUM COOLED FAST REACTORS
title_sort multiphysics simulation suite for sodium cooled fast reactors
publisher EDP Sciences
series EPJ Web of Conferences
issn 2100-014X
publishDate 2021-01-01
description A simulation suite has been developed to model reactor power distribution and multiphysics feedback effects in Sodium-cooled Fast Reactors (SFRs). This suite is based on the Finite Element Method (FEM) and employs a general, unstructured mesh to solve the Simplified P3 (SP3) neutron transport equations. In the FEM implementation, two-dimensional triangular elements and three-dimensional wedge elements are selected. Wedge elements are selected for their natural description of hexagonal geometry common to fast reactors. Thermal feedback effects within fast reactors are modeled within the simulation suite. A thermal hydraulic model is developed, modeling both axial heat convection and radial heat conduction within fuel assemblies. A thermal expansion model is included and is demonstrated to significantly affect reactivity. This simulation suite has been employed to model the Advanced Burner Reactor (ABR) benchmark, specifically the MET-1000. It has been demonstrated that these models sufficiently describe the multiphysics feedback phenomena and can be used to estimate multiphysics reactivity feedback coefficients.
topic sodium-cooled fast reactor (sfr)
simplified pn (spn)
finite element method (fem)
thermal hydraulics
thermal expansion
multiphysics
url https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06019.pdf
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