Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

Fajar Sri Lestari Pangukir; Dirk Visser; Ferry Roelofs; Julio Pacio; Katrien Van Tichelen

doi:10.13182/NURETH20-40106

Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

Fajar Sri Lestari Pangukir, Dirk Visser, Ferry Roelofs, Julio Pacio, Katrien Van Tichelen

Research output › peer-review

Abstract

The liquid metal-cooled reactor is a Generation IV reactor concept aiming to provide safe, economic and sustainable nuclear energy in future. Understanding the thermal-hydraulic phenomena occurring in a liquid metal reactors pool, such as convection patterns, thermal mixing and stratification in operational and accidental conditions, is of primary importance and has been one of the main topics in past and present collaborative research projects. The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale model of the MYRRHA reactor, an accelerator-driven system cooled by lead-bismuth eutectic (LBE) and under development by SCK CEN in Belgium. The E-SCAPE experimental facility has been specially designed and constructed to get insight into the pool thermal-hydraulic behaviour, producing data for validation of computer codes and supporting the design of MYRRHA. Within the ongoing European project PASCAL, NRG will perform multi-scale simulations of asymmetric flow scenarios by coupling the system code SPECTRA to a CFD code. As a first step towards a fully coupled simulation, a model of E-SCAPE in SPECTRA and Star-CCM+ are constructed separately. In this paper, these stand-alone models are compared to each other for steady state E-SCAPE experiments at forced flow and a uniform temperature of 180 C. The codes show good agreement under these conditions, which will be beneficial for a smooth and stable coupling.

Original language	English
Title of host publication	20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)
Publisher	American Nuclear Society
Pages	5048-5057
Number of pages	10
Edition	2023
DOIs	https://doi.org/10.13182/NURETH20-40106
State	Published - 25 Aug 2023
Event	2023 - NURETH: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Washington Hilton, Washington D.C. Duration: 20 Aug 2023 → 25 Aug 2023 https://www.ans.org/meetings/nureth20/

Conference

Conference	2023 - NURETH
Abbreviated title	NURETH-20
Country/Territory	United States
City	Washington D.C.
Period	2023-08-20 → 2023-08-25
Internet address	https://www.ans.org/meetings/nureth20/

Access to Document

10.13182/NURETH20-40106License: Unspecified

Cite this

Pangukir, F. S. L., Visser, D., Roelofs, F., Pacio, J., & Van Tichelen, K. (2023). Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions. In 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20) (2023 ed., pp. 5048-5057). Article 54467 American Nuclear Society. https://doi.org/10.13182/NURETH20-40106

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title = "Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions",

abstract = "The liquid metal-cooled reactor is a Generation IV reactor concept aiming to provide safe, economic and sustainable nuclear energy in future. Understanding the thermal-hydraulic phenomena occurring in a liquid metal reactors pool, such as convection patterns, thermal mixing and stratification in operational and accidental conditions, is of primary importance and has been one of the main topics in past and present collaborative research projects. The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale model of the MYRRHA reactor, an accelerator-driven system cooled by lead-bismuth eutectic (LBE) and under development by SCK CEN in Belgium. The E-SCAPE experimental facility has been specially designed and constructed to get insight into the pool thermal-hydraulic behaviour, producing data for validation of computer codes and supporting the design of MYRRHA. Within the ongoing European project PASCAL, NRG will perform multi-scale simulations of asymmetric flow scenarios by coupling the system code SPECTRA to a CFD code. As a first step towards a fully coupled simulation, a model of E-SCAPE in SPECTRA and Star-CCM+ are constructed separately. In this paper, these stand-alone models are compared to each other for steady state E-SCAPE experiments at forced flow and a uniform temperature of 180 C. The codes show good agreement under these conditions, which will be beneficial for a smooth and stable coupling.",

keywords = "Liquid metal, E-SCAPE, TH Model, SPECTRA",

author = "Pangukir, {Fajar Sri Lestari} and Dirk Visser and Ferry Roelofs and Julio Pacio and {Van Tichelen}, Katrien",

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Pangukir, FSL, Visser, D, Roelofs, F, Pacio, J & Van Tichelen, K 2023, Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions. in 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20). 2023 edn, 54467, American Nuclear Society, pp. 5048-5057, 2023 - NURETH, Washington D.C., Washington, United States, 2023-08-20. https://doi.org/10.13182/NURETH20-40106

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T1 - Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

AU - Pangukir, Fajar Sri Lestari

AU - Visser, Dirk

AU - Roelofs, Ferry

AU - Pacio, Julio

AU - Van Tichelen, Katrien

N1 - Score=3

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N2 - The liquid metal-cooled reactor is a Generation IV reactor concept aiming to provide safe, economic and sustainable nuclear energy in future. Understanding the thermal-hydraulic phenomena occurring in a liquid metal reactors pool, such as convection patterns, thermal mixing and stratification in operational and accidental conditions, is of primary importance and has been one of the main topics in past and present collaborative research projects. The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale model of the MYRRHA reactor, an accelerator-driven system cooled by lead-bismuth eutectic (LBE) and under development by SCK CEN in Belgium. The E-SCAPE experimental facility has been specially designed and constructed to get insight into the pool thermal-hydraulic behaviour, producing data for validation of computer codes and supporting the design of MYRRHA. Within the ongoing European project PASCAL, NRG will perform multi-scale simulations of asymmetric flow scenarios by coupling the system code SPECTRA to a CFD code. As a first step towards a fully coupled simulation, a model of E-SCAPE in SPECTRA and Star-CCM+ are constructed separately. In this paper, these stand-alone models are compared to each other for steady state E-SCAPE experiments at forced flow and a uniform temperature of 180 C. The codes show good agreement under these conditions, which will be beneficial for a smooth and stable coupling.

AB - The liquid metal-cooled reactor is a Generation IV reactor concept aiming to provide safe, economic and sustainable nuclear energy in future. Understanding the thermal-hydraulic phenomena occurring in a liquid metal reactors pool, such as convection patterns, thermal mixing and stratification in operational and accidental conditions, is of primary importance and has been one of the main topics in past and present collaborative research projects. The European Scaled Pool Experiment (E-SCAPE) is a 1/6th-scale model of the MYRRHA reactor, an accelerator-driven system cooled by lead-bismuth eutectic (LBE) and under development by SCK CEN in Belgium. The E-SCAPE experimental facility has been specially designed and constructed to get insight into the pool thermal-hydraulic behaviour, producing data for validation of computer codes and supporting the design of MYRRHA. Within the ongoing European project PASCAL, NRG will perform multi-scale simulations of asymmetric flow scenarios by coupling the system code SPECTRA to a CFD code. As a first step towards a fully coupled simulation, a model of E-SCAPE in SPECTRA and Star-CCM+ are constructed separately. In this paper, these stand-alone models are compared to each other for steady state E-SCAPE experiments at forced flow and a uniform temperature of 180 C. The codes show good agreement under these conditions, which will be beneficial for a smooth and stable coupling.

KW - Liquid metal

KW - E-SCAPE

KW - TH Model

KW - SPECTRA

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/57682813

U2 - 10.13182/NURETH20-40106

DO - 10.13182/NURETH20-40106

M3 - In-proceedings paper

SP - 5048

EP - 5057

BT - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)

PB - American Nuclear Society

T2 - 2023 - NURETH

Y2 - 20 August 2023 through 25 August 2023

ER -