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

Ken and Mary Alice Lindquist Department of Nuclear Engineering

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

1 Scopus citations

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
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

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering
Instrumentation

Access to Document

10.13182/NURETH20-40462

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

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).

@inproceedings{30e107245fb54775b9da17edc805fe68,

title = "NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS",

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.",

author = "Novak, {A. J.} and Dutra, {C. Bourdot} and D. Shaver and E. Merzari",

note = "Publisher Copyright: {\textcopyright} 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.; 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023 ; Conference date: 20-08-2023 Through 25-08-2023",

year = "2023",

doi = "10.13182/NURETH20-40462",

language = "English (US)",

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

publisher = "American Nuclear Society",

pages = "3030--3043",

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

address = "United States",

}

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

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

TY - GEN

T1 - NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS

AU - Novak, A. J.

AU - Dutra, C. Bourdot

AU - Shaver, D.

AU - Merzari, E.

PY - 2023

Y1 - 2023

N2 - 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.

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.

UR - http://www.scopus.com/inward/record.url?scp=85202930175&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85202930175&partnerID=8YFLogxK

U2 - 10.13182/NURETH20-40462

DO - 10.13182/NURETH20-40462

M3 - Conference contribution

AN - SCOPUS:85202930175

T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

SP - 3030

EP - 3043

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

PB - American Nuclear Society

T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023

Y2 - 20 August 2023 through 25 August 2023

ER -

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

NEKRS CFD SIMULATIONS OF INTERASSEMBLY FLOW IN SODIUM FAST REACTORS

Abstract

Publication series

Conference

All Science Journal Classification (ASJC) codes

Access to Document

Other files and links

Fingerprint

Cite this