CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE)

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CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE). / Lopes, Silvania; Koloszar, Lila; Planquart, Philippe; Van Tichelen, Katrien; Keijers, Steven.

The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) . SCK CEN, 2022. p. 1-14 35782.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Lopes, S, Koloszar, L, Planquart, P, Van Tichelen, K & Keijers, S 2022, CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE). in The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) ., 35782, SCK CEN, pp. 1-14, 2022 - NURETH - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Brussels, Belgium, 2022-03-06.

APA

Lopes, S., Koloszar, L., Planquart, P., Van Tichelen, K., & Keijers, S. (2022). CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE). In The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (pp. 1-14). [35782] SCK CEN.

Vancouver

Lopes S, Koloszar L, Planquart P, Van Tichelen K, Keijers S. CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE). In The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) . SCK CEN. 2022. p. 1-14. 35782

Author

Lopes, Silvania ; Koloszar, Lila ; Planquart, Philippe ; Van Tichelen, Katrien ; Keijers, Steven. / CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE). The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) . SCK CEN, 2022. pp. 1-14

Bibtex - Download

@inproceedings{cb76e3a4048c499c837961076901cc92,
title = "CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE)",
abstract = "This work presents the modeling approach and results obtained by VKI using Computational Fluid Dynamics (CFD) simulations of the flow and heat transport in E-SCAPE facility, which is a thermal hydraulic 1/6-scale model of the MYRRHA reactor. The paper focus on the effects of proper geometry representation and refining mesh in the core region, for the correct prediction of the pressure drop in the system, which has a direct consequence on the evolution of the mass flows and determines the free-surface levels in transient scenarios. CFD analysis of the flow and thermal field for different forced flow conditions are also presented and predicted temperature distribution in the pool, core and plena are compared with experimental results. The comparison between the numerical and experimental data are discussed and guidelines are proposed for CFD simulation of a pool type liquid metal reactor.",
keywords = "Thermal-hydraulics, Pressure drop, E-SCAPE, MYRRHA reactor, RANS",
author = "Silvania Lopes and Lila Koloszar and Philippe Planquart and {Van Tichelen}, Katrien and Steven Keijers",
note = "Score=3; 2022 - NURETH - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics ; Conference date: 06-03-2022 Through 11-03-2022",
year = "2022",
month = mar,
day = "6",
language = "English",
pages = "1--14",
booktitle = "The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)",
publisher = "SCK CEN",
address = "Belgium",
url = "http://www.nureth19.com",

}

RIS - Download

TY - GEN

T1 - CFD simulation of the heavy liquid European scaled pool experiment (E-SCAPE)

AU - Lopes, Silvania

AU - Koloszar, Lila

AU - Planquart, Philippe

AU - Van Tichelen, Katrien

AU - Keijers, Steven

N1 - Conference code: NURETH19

PY - 2022/3/6

Y1 - 2022/3/6

N2 - This work presents the modeling approach and results obtained by VKI using Computational Fluid Dynamics (CFD) simulations of the flow and heat transport in E-SCAPE facility, which is a thermal hydraulic 1/6-scale model of the MYRRHA reactor. The paper focus on the effects of proper geometry representation and refining mesh in the core region, for the correct prediction of the pressure drop in the system, which has a direct consequence on the evolution of the mass flows and determines the free-surface levels in transient scenarios. CFD analysis of the flow and thermal field for different forced flow conditions are also presented and predicted temperature distribution in the pool, core and plena are compared with experimental results. The comparison between the numerical and experimental data are discussed and guidelines are proposed for CFD simulation of a pool type liquid metal reactor.

AB - This work presents the modeling approach and results obtained by VKI using Computational Fluid Dynamics (CFD) simulations of the flow and heat transport in E-SCAPE facility, which is a thermal hydraulic 1/6-scale model of the MYRRHA reactor. The paper focus on the effects of proper geometry representation and refining mesh in the core region, for the correct prediction of the pressure drop in the system, which has a direct consequence on the evolution of the mass flows and determines the free-surface levels in transient scenarios. CFD analysis of the flow and thermal field for different forced flow conditions are also presented and predicted temperature distribution in the pool, core and plena are compared with experimental results. The comparison between the numerical and experimental data are discussed and guidelines are proposed for CFD simulation of a pool type liquid metal reactor.

KW - Thermal-hydraulics

KW - Pressure drop

KW - E-SCAPE

KW - MYRRHA reactor

KW - RANS

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/49004550

M3 - In-proceedings paper

SP - 1

EP - 14

BT - The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)

PB - SCK CEN

T2 - 2022 - NURETH - 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics

Y2 - 6 March 2022 through 11 March 2022

ER -

ID: 7536314