Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review
The boiling process is utterly fundamental to the design and safety of water-cooled fission reactors. Both boiling water reactors and pressurised water reactors use boiling under high-pressure subcooled liquid flow conditions to achieve high surface heat fluxes required for their operation. Liquid w...
| Main Author: | |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
MDPI AG
2020-09-01
|
| Series: | Inventions |
| Subjects: | |
| Online Access: | https://www.mdpi.com/2411-5134/5/3/47 |
| _version_ | 1797553783276830720 |
|---|---|
| author | Giovanni Giustini |
| author_facet | Giovanni Giustini |
| author_sort | Giovanni Giustini |
| collection | DOAJ |
| description | The boiling process is utterly fundamental to the design and safety of water-cooled fission reactors. Both boiling water reactors and pressurised water reactors use boiling under high-pressure subcooled liquid flow conditions to achieve high surface heat fluxes required for their operation. Liquid water is an excellent coolant, which is why water-cooled reactors can have such small sizes and high-power densities, yet also have relatively low component temperatures. Steam is in contrast a very poor coolant. A good understanding of how liquid water coolant turns into steam is correspondingly vital. This need is particularly pressing because heat transfer by water when it is only partially steam (‘nucleate boiling’ regime) is particularly effective, providing a great incentive to operate a plant in this regime. Computational modelling of boiling, using computational fluid dynamics (CFD) simulation at the ‘component scale’ typical of nuclear subchannel analysis and at the scale of the single bubbles, is a core activity of current nuclear thermal hydraulics research. This paper gives an overview of recent literature on computational modelling of boiling. The knowledge and capabilities embodied in the surveyed literature entail theoretical, experimental and modelling work, and enabled the scientific community to improve its current understanding of the fundamental heat transfer phenomena in boiling fluids and to develop more accurate tools for the prediction of two-phase cooling in nuclear systems. Data and insights gathered on the fundamental heat transfer processes associated with the behaviour of single bubbles enabled us to develop and apply more capable modelling tools for engineering simulation and to obtain reliable estimates of the heat transfer rates associated with the growth and departure of steam bubbles from heated surfaces. While results so far are promising, much work is still needed in terms of development of fundamental understanding of the physical processes and application of improved modelling capabilities to industrially relevant flows. |
| first_indexed | 2024-03-10T16:21:33Z |
| format | Article |
| id | doaj.art-6c6af40450754366ac412e6bb4f0c0d8 |
| institution | Directory Open Access Journal |
| issn | 2411-5134 |
| language | English |
| last_indexed | 2024-03-10T16:21:33Z |
| publishDate | 2020-09-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Inventions |
| spelling | doaj.art-6c6af40450754366ac412e6bb4f0c0d82023-11-20T13:37:13ZengMDPI AGInventions2411-51342020-09-01534710.3390/inventions5030047Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief ReviewGiovanni Giustini0Mechanical Engineering Department, Imperial College London, London SW7 2AZ, UKThe boiling process is utterly fundamental to the design and safety of water-cooled fission reactors. Both boiling water reactors and pressurised water reactors use boiling under high-pressure subcooled liquid flow conditions to achieve high surface heat fluxes required for their operation. Liquid water is an excellent coolant, which is why water-cooled reactors can have such small sizes and high-power densities, yet also have relatively low component temperatures. Steam is in contrast a very poor coolant. A good understanding of how liquid water coolant turns into steam is correspondingly vital. This need is particularly pressing because heat transfer by water when it is only partially steam (‘nucleate boiling’ regime) is particularly effective, providing a great incentive to operate a plant in this regime. Computational modelling of boiling, using computational fluid dynamics (CFD) simulation at the ‘component scale’ typical of nuclear subchannel analysis and at the scale of the single bubbles, is a core activity of current nuclear thermal hydraulics research. This paper gives an overview of recent literature on computational modelling of boiling. The knowledge and capabilities embodied in the surveyed literature entail theoretical, experimental and modelling work, and enabled the scientific community to improve its current understanding of the fundamental heat transfer phenomena in boiling fluids and to develop more accurate tools for the prediction of two-phase cooling in nuclear systems. Data and insights gathered on the fundamental heat transfer processes associated with the behaviour of single bubbles enabled us to develop and apply more capable modelling tools for engineering simulation and to obtain reliable estimates of the heat transfer rates associated with the growth and departure of steam bubbles from heated surfaces. While results so far are promising, much work is still needed in terms of development of fundamental understanding of the physical processes and application of improved modelling capabilities to industrially relevant flows.https://www.mdpi.com/2411-5134/5/3/47nuclearthermal-hydraulicstwo-phase flowboiling |
| spellingShingle | Giovanni Giustini Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review Inventions nuclear thermal-hydraulics two-phase flow boiling |
| title | Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review |
| title_full | Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review |
| title_fullStr | Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review |
| title_full_unstemmed | Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review |
| title_short | Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review |
| title_sort | modelling of boiling flows for nuclear thermal hydraulics applications a brief review |
| topic | nuclear thermal-hydraulics two-phase flow boiling |
| url | https://www.mdpi.com/2411-5134/5/3/47 |
| work_keys_str_mv | AT giovannigiustini modellingofboilingflowsfornuclearthermalhydraulicsapplicationsabriefreview |