NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS

A. J. Novak; C. Bourdot Dutra; D. Shaver; E. Merzari

doi:10.13182/NURETH20-40462

NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS

A. J. Novak, C. Bourdot Dutra, D. Shaver, E. Merzari

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Abstract

Interassembly flow in Sodium Fast Reactors (SFRs) represents a bypass flow path exterior to the fuel assembly ducts.Heat transferred across this thin laminar-transitional gap is an important component of core radial expansion, where the coupling between thermal-fluids, neutronics, and solid mechanics results in time-dependent duct bowing.These geometry changes can constitute a significant portion of the total reactivity response in transients, but are difficult to model to high-fidelity.To improve our understanding of interassembly flow, this paper provides preliminary NekRS Reynolds Averaged Navier-Stokes (RANS) and Large Eddy Simulations (LES) of the interassembly flow in a 19-bundle core.We predict velocity distributions and illustrate a multiscale postprocessing system that can be used to generate coarse-mesh closures for subchannel and porous media tools.

Original language	English (US)
Title of host publication	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Publisher	American Nuclear Society
Pages	3030-3043
Number of pages	14
ISBN (Electronic)	9780894487934
DOIs	https://doi.org/10.13182/NURETH20-40462
State	Published - 2023
Externally published	Yes
Event	20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 - Washington, United States Duration: Aug 20 2023 → Aug 25 2023

Publication series

Name	Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Conference

Conference	20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Country/Territory	United States
City	Washington
Period	8/20/23 → 8/25/23

Keywords

Cardinal
CFD
NekRS
SFR

ASJC Scopus subject areas

Nuclear Energy and Engineering
Instrumentation

Online availability

10.13182/NURETH20-40462

Library availability

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Cite this

Novak, A. J., Dutra, C. B., Shaver, D., & Merzari, E. (2023). NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS. In Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 (pp. 3030-3043). (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023). American Nuclear Society. https://doi.org/10.13182/NURETH20-40462

NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS. / Novak, A. J.; Dutra, C. Bourdot; Shaver, D. et al.
Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, 2023. p. 3030-3043 (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Novak, AJ, Dutra, CB, Shaver, D & Merzari, E 2023, NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS. in Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, American Nuclear Society, pp. 3030-3043, 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, Washington, United States, 8/20/23. https://doi.org/10.13182/NURETH20-40462

Novak AJ, Dutra CB, Shaver D, Merzari E. NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS. In Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society. 2023. p. 3030-3043. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023). doi: 10.13182/NURETH20-40462

Novak, A. J. ; Dutra, C. Bourdot ; Shaver, D. et al. / NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS. Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, 2023. pp. 3030-3043 (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).

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abstract = "Interassembly flow in Sodium Fast Reactors (SFRs) represents a bypass flow path exterior to the fuel assembly ducts.Heat transferred across this thin laminar-transitional gap is an important component of core radial expansion, where the coupling between thermal-fluids, neutronics, and solid mechanics results in time-dependent duct bowing.These geometry changes can constitute a significant portion of the total reactivity response in transients, but are difficult to model to high-fidelity.To improve our understanding of interassembly flow, this paper provides preliminary NekRS Reynolds Averaged Navier-Stokes (RANS) and Large Eddy Simulations (LES) of the interassembly flow in a 19-bundle core.We predict velocity distributions and illustrate a multiscale postprocessing system that can be used to generate coarse-mesh closures for subchannel and porous media tools.",

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AB - Interassembly flow in Sodium Fast Reactors (SFRs) represents a bypass flow path exterior to the fuel assembly ducts.Heat transferred across this thin laminar-transitional gap is an important component of core radial expansion, where the coupling between thermal-fluids, neutronics, and solid mechanics results in time-dependent duct bowing.These geometry changes can constitute a significant portion of the total reactivity response in transients, but are difficult to model to high-fidelity.To improve our understanding of interassembly flow, this paper provides preliminary NekRS Reynolds Averaged Navier-Stokes (RANS) and Large Eddy Simulations (LES) of the interassembly flow in a 19-bundle core.We predict velocity distributions and illustrate a multiscale postprocessing system that can be used to generate coarse-mesh closures for subchannel and porous media tools.

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NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS

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