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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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 |
work_keys_str_mv |
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