Abstract
Subcooled nucleate boiling capability was introduced to OpenFOAM 4.0 within the multiphase framework called reactingEulerFoam. Since then the capability has been further refined and extended in subsequent releases 5.0 and 6. The present implementation - available in OpenFOAM Foundation development release - includes the RPI wall boiling model with run time selectable nucleation site density and bubble departure diameter and frequency models. Runtime selectable wall heat transfer models for distribution of wall heat flux between gas and liquid phases are also included for non-equilibrium phase change simulations. Interfacial heat transfer and phase change are calculated with a two-resistance approach using user selectable heat transfer and saturation temperature models. For bubble diameter modelling algebraic, IATE and inhomogeneous class method models are supported. The present paper provides an overview of the thermal phase change modelling and related models and their implementation and compares simulation results obtained with different model combinations to publicly available experimental data from DEBORA experiments. The goal is to aid those that intend to use the publicly available reactingEulerFoam by providing a summary of the available models and demonstrations of a few modelling details. Tutorial cases based on the presented simulations will be made publicly available in future releases.
| Original language | English |
|---|---|
| Title of host publication | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
| Publisher | American Nuclear Society ANS |
| Pages | 2149-2163 |
| Number of pages | 15 |
| Edition | cd-rom |
| ISBN (Electronic) | 978-0-89448-767-5 |
| Publication status | Published - 1 Jan 2019 |
| MoE publication type | A4 Article in a conference publication |
| Event | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States Duration: 18 Aug 2019 → 23 Aug 2019 |
Conference
| Conference | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 |
|---|---|
| Abbreviated title | NURETH-18 |
| Country | United States |
| City | Portland |
| Period | 18/08/19 → 23/08/19 |
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Keywords
- CFD
- Condensation
- OpenFOAM
- Size distribution
- Subcooled boiling
Cite this
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On development and validation of subcooled nucleate boiling models for openfoam foundation release. / Peltola, J.; Pättikangas, T.; Bainbridge, W.; Lehnigk, R.; Schlegel, F.
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. cd-rom. ed. American Nuclear Society ANS, 2019. p. 2149-2163.Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review
TY - GEN
T1 - On development and validation of subcooled nucleate boiling models for openfoam foundation release
AU - Peltola, J.
AU - Pättikangas, T.
AU - Bainbridge, W.
AU - Lehnigk, R.
AU - Schlegel, F.
PY - 2019/1/1
Y1 - 2019/1/1
N2 - Subcooled nucleate boiling capability was introduced to OpenFOAM 4.0 within the multiphase framework called reactingEulerFoam. Since then the capability has been further refined and extended in subsequent releases 5.0 and 6. The present implementation - available in OpenFOAM Foundation development release - includes the RPI wall boiling model with run time selectable nucleation site density and bubble departure diameter and frequency models. Runtime selectable wall heat transfer models for distribution of wall heat flux between gas and liquid phases are also included for non-equilibrium phase change simulations. Interfacial heat transfer and phase change are calculated with a two-resistance approach using user selectable heat transfer and saturation temperature models. For bubble diameter modelling algebraic, IATE and inhomogeneous class method models are supported. The present paper provides an overview of the thermal phase change modelling and related models and their implementation and compares simulation results obtained with different model combinations to publicly available experimental data from DEBORA experiments. The goal is to aid those that intend to use the publicly available reactingEulerFoam by providing a summary of the available models and demonstrations of a few modelling details. Tutorial cases based on the presented simulations will be made publicly available in future releases.
AB - Subcooled nucleate boiling capability was introduced to OpenFOAM 4.0 within the multiphase framework called reactingEulerFoam. Since then the capability has been further refined and extended in subsequent releases 5.0 and 6. The present implementation - available in OpenFOAM Foundation development release - includes the RPI wall boiling model with run time selectable nucleation site density and bubble departure diameter and frequency models. Runtime selectable wall heat transfer models for distribution of wall heat flux between gas and liquid phases are also included for non-equilibrium phase change simulations. Interfacial heat transfer and phase change are calculated with a two-resistance approach using user selectable heat transfer and saturation temperature models. For bubble diameter modelling algebraic, IATE and inhomogeneous class method models are supported. The present paper provides an overview of the thermal phase change modelling and related models and their implementation and compares simulation results obtained with different model combinations to publicly available experimental data from DEBORA experiments. The goal is to aid those that intend to use the publicly available reactingEulerFoam by providing a summary of the available models and demonstrations of a few modelling details. Tutorial cases based on the presented simulations will be made publicly available in future releases.
KW - CFD
KW - Condensation
KW - OpenFOAM
KW - Size distribution
KW - Subcooled boiling
UR - http://www.scopus.com/inward/record.url?scp=85073729488&partnerID=8YFLogxK
M3 - Conference article in proceedings
AN - SCOPUS:85073729488
SP - 2149
EP - 2163
BT - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
PB - American Nuclear Society ANS
ER -