MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

Lilla Koloszar; Sophia Buckingham; Steven Keijers

MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA

Lilla Koloszar, Sophia Buckingham, Steven Keijers

Research output › peer-review

Abstract

Numerical analysis of the thermohydraulic behavior of the innovative flexible fast spectrum research reactor, MYRRHA, under design by the Belgian Nuclear Research center (SCK'CEN) is a very challenging task. The primary coolant of the reactor is Lead Bismuth Eutectic, LBE, which is an opaque heavy liquid metal with low Prandtl number. The simulation tool needs to involve many complex physical phenomena to be able to predict accurately the flow and thermal field in the pool type reactor. In the past few years, within the frame of a collaboration between SCK'CEN and the von Karman Institute, a new platform, MyrrhaFoam, was developed based on the open source simulation environment, OpenFOAM. The current tool can deal with incompressible buoyancy corrected steady/unsteady single phase flows. It takes into account conjugate heat transfer in the solid parts which is mandatory due to the expected high temperature gradients between the different parts of the reactor. The temperature dependent properties of LBE are also considered. MyrrhaFoam is supplemented with the most relevant thermal turbulence models for low Prandtl number liquids up to date.

Original language	English
Title of host publication	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Publisher	American Nuclear Society
Pages	2237-2250
Number of pages	14
Volume	3
ISBN (Electronic)	9781510811843
State	Published - Sep 2015
Event	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago Duration: 30 Aug 2015 → 4 Sep 2015

Publication series

Name	International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume	3

Conference

Conference	16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/Territory	United States
City	Chicago
Period	2015-08-30 → 2015-09-04

ASJC Scopus subject areas

Instrumentation
Nuclear Energy and Engineering

Access to Document

https://www.scopus.com/record/display.uri?eid=2-s2.0-84962694314&origin=inward&txGid=18b1e6fb5d8e4a2db179c17733f06634License: Unspecified

Cite this

Koloszar, L., Buckingham, S., & Keijers, S. (2015). MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA. In International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015 (Vol. 3, pp. 2237-2250). (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 3). American Nuclear Society. https://www.scopus.com/record/display.uri?eid=2-s2.0-84962694314&origin=inward&txGid=18b1e6fb5d8e4a2db179c17733f06634

Koloszar, Lilla ; Buckingham, Sophia ; Keijers, Steven. / MYRRHA foam : A CFD model for the study of the thermal hydraulic behavior of MYRRHA. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 3 American Nuclear Society, 2015. pp. 2237-2250 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015).

@inproceedings{b0019714a5ff402295927331da34d5d4,

title = "MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA",

abstract = "Numerical analysis of the thermohydraulic behavior of the innovative flexible fast spectrum research reactor, MYRRHA, under design by the Belgian Nuclear Research center (SCK'CEN) is a very challenging task. The primary coolant of the reactor is Lead Bismuth Eutectic, LBE, which is an opaque heavy liquid metal with low Prandtl number. The simulation tool needs to involve many complex physical phenomena to be able to predict accurately the flow and thermal field in the pool type reactor. In the past few years, within the frame of a collaboration between SCK'CEN and the von Karman Institute, a new platform, MyrrhaFoam, was developed based on the open source simulation environment, OpenFOAM. The current tool can deal with incompressible buoyancy corrected steady/unsteady single phase flows. It takes into account conjugate heat transfer in the solid parts which is mandatory due to the expected high temperature gradients between the different parts of the reactor. The temperature dependent properties of LBE are also considered. MyrrhaFoam is supplemented with the most relevant thermal turbulence models for low Prandtl number liquids up to date.",

keywords = "Computational fluid dynamics, Fast reactors, Heat transfer, Liquid metals",

author = "Lilla Koloszar and Sophia Buckingham and Steven Keijers",

note = "Publisher Copyright: {\textcopyright} Copyright (2015) by American Nuclear Society All rights reserved.; 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 ; Conference date: 30-08-2015 Through 04-09-2015",

year = "2015",

month = sep,

language = "English",

volume = "3",

series = "International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015",

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Koloszar, L, Buckingham, S & Keijers, S 2015, MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA. in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. vol. 3, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, vol. 3, American Nuclear Society, pp. 2237-2250, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States, 2015-08-30. <https://www.scopus.com/record/display.uri?eid=2-s2.0-84962694314&origin=inward&txGid=18b1e6fb5d8e4a2db179c17733f06634>

MYRRHA foam: A CFD model for the study of the thermal hydraulic behavior of MYRRHA. / Koloszar, Lilla; Buckingham, Sophia; Keijers, Steven.
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. Vol. 3 American Nuclear Society, 2015. p. 2237-2250 (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; Vol. 3).

Research output › peer-review

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AU - Buckingham, Sophia

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N2 - Numerical analysis of the thermohydraulic behavior of the innovative flexible fast spectrum research reactor, MYRRHA, under design by the Belgian Nuclear Research center (SCK'CEN) is a very challenging task. The primary coolant of the reactor is Lead Bismuth Eutectic, LBE, which is an opaque heavy liquid metal with low Prandtl number. The simulation tool needs to involve many complex physical phenomena to be able to predict accurately the flow and thermal field in the pool type reactor. In the past few years, within the frame of a collaboration between SCK'CEN and the von Karman Institute, a new platform, MyrrhaFoam, was developed based on the open source simulation environment, OpenFOAM. The current tool can deal with incompressible buoyancy corrected steady/unsteady single phase flows. It takes into account conjugate heat transfer in the solid parts which is mandatory due to the expected high temperature gradients between the different parts of the reactor. The temperature dependent properties of LBE are also considered. MyrrhaFoam is supplemented with the most relevant thermal turbulence models for low Prandtl number liquids up to date.

AB - Numerical analysis of the thermohydraulic behavior of the innovative flexible fast spectrum research reactor, MYRRHA, under design by the Belgian Nuclear Research center (SCK'CEN) is a very challenging task. The primary coolant of the reactor is Lead Bismuth Eutectic, LBE, which is an opaque heavy liquid metal with low Prandtl number. The simulation tool needs to involve many complex physical phenomena to be able to predict accurately the flow and thermal field in the pool type reactor. In the past few years, within the frame of a collaboration between SCK'CEN and the von Karman Institute, a new platform, MyrrhaFoam, was developed based on the open source simulation environment, OpenFOAM. The current tool can deal with incompressible buoyancy corrected steady/unsteady single phase flows. It takes into account conjugate heat transfer in the solid parts which is mandatory due to the expected high temperature gradients between the different parts of the reactor. The temperature dependent properties of LBE are also considered. MyrrhaFoam is supplemented with the most relevant thermal turbulence models for low Prandtl number liquids up to date.

KW - Computational fluid dynamics

KW - Fast reactors

KW - Heat transfer

KW - Liquid metals

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T3 - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

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BT - International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015

PB - American Nuclear Society

Y2 - 30 August 2015 through 4 September 2015

ER -