Imperial College London
Portrait Picture

Dr Giovanni Giustini

Faculty of Engineering, Department of Mechanical Engineering

Honorary Lecturer
 
 
 
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Contact

 

+44 (0)20 7594 9681g.giustini12 Website

 
 
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Location

 

City and Guilds BuildingSouth Kensington Campus

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Summary

 

Publications

Citation

BibTex format

@article{Giustini:2020:10.3390/inventions5030047,
author = {Giustini, G},
doi = {10.3390/inventions5030047},
journal = {Inventions},
pages = {1--18},
title = {Modelling of boiling flows for nuclear thermal hydraulics applications—a brief review},
url = {http://dx.doi.org/10.3390/inventions5030047},
volume = {5},
year = {2020}
}
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RIS format (EndNote, RefMan)

TY  - JOUR
AB  - 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 understandi
AU  - Giustini,G
DO  - 10.3390/inventions5030047
EP  - 18
PY  - 2020///
SN  - 2411-5134
SP  - 1
TI  - Modelling of boiling flows for nuclear thermal hydraulics applications—a brief review
T2  - Inventions
UR  - http://dx.doi.org/10.3390/inventions5030047
UR  - https://www.mdpi.com/2411-5134/5/3/47
UR  - http://hdl.handle.net/10044/1/84576
VL  - 5
ER  -
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