Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant

An accurate prediction of the interphase behaviors of the vertical gas-liquid subcooled boiling flow is meaningful for the first loop of a nuclear power plant (NPP). Therefore, the interphase behaviors including the bubble size distribution in the first loop of the NPP are analyzed, evaluated, and v...

Descripción completa

Guardado en:

Detalles Bibliográficos
Autores principales:	Guang Hu, Yue Ma, Qianfeng Liu
Formato:	article
Lenguaje:	EN
Publicado:	MDPI AG 2021
Materias:	wall boiling subcooled boiling population balance model bubble condensation bubble coalescence and breakup first loop Technology T
Acceso en línea:	https://doaj.org/article/465c6281aabf4abd854b5a0f392f7a49
Etiquetas:	Agregar Etiqueta Sin Etiquetas, Sea el primero en etiquetar este registro!

id	oai:doaj.org-article:465c6281aabf4abd854b5a0f392f7a49
record_format	dspace
spelling	oai:doaj.org-article:465c6281aabf4abd854b5a0f392f7a492021-11-11T16:04:41ZEvaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant10.3390/en142173571996-1073https://doaj.org/article/465c6281aabf4abd854b5a0f392f7a492021-11-01T00:00:00Zhttps://www.mdpi.com/1996-1073/14/21/7357https://doaj.org/toc/1996-1073An accurate prediction of the interphase behaviors of the vertical gas-liquid subcooled boiling flow is meaningful for the first loop of a nuclear power plant (NPP). Therefore, the interphase behaviors including the bubble size distribution in the first loop of the NPP are analyzed, evaluated, and validated using various wall boiling models coupled with the population balance model (PBM) kernels in this paper. Firstly, nondimensional numbers of the first loop of the NPP and DEBORA (Development of Borehole Seals for High-Level Radioactive Waste) experiment test cases are analyzed with approximation. Secondly, five active nucleation site density models <i>N</i><sub>n</sub> coupled with the PBM kernel combination, four kernel combinations (C1~C4) with the <i>N</i><sub>n</sub> models are calculated and analyzed. Lastly, various behaviors including the bubble size distribution Sauter mean diameter (SMD) <i>d</i><sub>p</sub>, void fraction <i>α</i>, gas superficial velocity <i>j</i><sub>g</sub>, and liquid superficial velocity <i>j</i><sub>l</sub> are compared and validated with the experimental data of the DEBORA-1 (<i>P</i> = 2.62 MPa). The results indicate that the two <i>N</i><sub>n</sub> models are suitable for the calculations of thefirst loop of the nuclear power plant. For instance, for the bubble size distribution SMD <i>d</i><sub>p</sub>, the specified <i>N</i><sub>n</sub> model with C1 (maximum relative error 9.63%) has relatively better behaviors for the first loop of the NPP. Especially, the combination C1 is applicable for the calculation of the bubble size distribution <i>d</i><sub>p</sub>, void fraction <i>α</i> and liquid superficial velocity <i>j</i><sub>l</sub> while C4 is suitable for the calculation of the gas superficial velocity <i>j</i><sub>g</sub>. These results can provide guidance for the numerical computation of the subcooled boiling flow in the first loop of the NPP.Guang HuYue MaQianfeng LiuMDPI AGarticlewall boilingsubcooled boilingpopulation balance modelbubble condensationbubble coalescence and breakupfirst loopTechnologyTENEnergies, Vol 14, Iss 7357, p 7357 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	wall boiling subcooled boiling population balance model bubble condensation bubble coalescence and breakup first loop Technology T
spellingShingle	wall boiling subcooled boiling population balance model bubble condensation bubble coalescence and breakup first loop Technology T Guang Hu Yue Ma Qianfeng Liu Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
description	An accurate prediction of the interphase behaviors of the vertical gas-liquid subcooled boiling flow is meaningful for the first loop of a nuclear power plant (NPP). Therefore, the interphase behaviors including the bubble size distribution in the first loop of the NPP are analyzed, evaluated, and validated using various wall boiling models coupled with the population balance model (PBM) kernels in this paper. Firstly, nondimensional numbers of the first loop of the NPP and DEBORA (Development of Borehole Seals for High-Level Radioactive Waste) experiment test cases are analyzed with approximation. Secondly, five active nucleation site density models <i>N</i><sub>n</sub> coupled with the PBM kernel combination, four kernel combinations (C1~C4) with the <i>N</i><sub>n</sub> models are calculated and analyzed. Lastly, various behaviors including the bubble size distribution Sauter mean diameter (SMD) <i>d</i><sub>p</sub>, void fraction <i>α</i>, gas superficial velocity <i>j</i><sub>g</sub>, and liquid superficial velocity <i>j</i><sub>l</sub> are compared and validated with the experimental data of the DEBORA-1 (<i>P</i> = 2.62 MPa). The results indicate that the two <i>N</i><sub>n</sub> models are suitable for the calculations of thefirst loop of the nuclear power plant. For instance, for the bubble size distribution SMD <i>d</i><sub>p</sub>, the specified <i>N</i><sub>n</sub> model with C1 (maximum relative error 9.63%) has relatively better behaviors for the first loop of the NPP. Especially, the combination C1 is applicable for the calculation of the bubble size distribution <i>d</i><sub>p</sub>, void fraction <i>α</i> and liquid superficial velocity <i>j</i><sub>l</sub> while C4 is suitable for the calculation of the gas superficial velocity <i>j</i><sub>g</sub>. These results can provide guidance for the numerical computation of the subcooled boiling flow in the first loop of the NPP.
format	article
author	Guang Hu Yue Ma Qianfeng Liu
author_facet	Guang Hu Yue Ma Qianfeng Liu
author_sort	Guang Hu
title	Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
title_short	Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
title_full	Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
title_fullStr	Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
title_full_unstemmed	Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant
title_sort	evaluation on coupling of wall boiling and population balance models for vertical gas-liquid subcooled boiling flow of first loop of nuclear power plant
publisher	MDPI AG
publishDate	2021
url	https://doaj.org/article/465c6281aabf4abd854b5a0f392f7a49
work_keys_str_mv	AT guanghu evaluationoncouplingofwallboilingandpopulationbalancemodelsforverticalgasliquidsubcooledboilingflowoffirstloopofnuclearpowerplant AT yuema evaluationoncouplingofwallboilingandpopulationbalancemodelsforverticalgasliquidsubcooledboilingflowoffirstloopofnuclearpowerplant AT qianfengliu evaluationoncouplingofwallboilingandpopulationbalancemodelsforverticalgasliquidsubcooledboilingflowoffirstloopofnuclearpowerplant
_version_	1718432409929646080

Evaluation on Coupling of Wall Boiling and Population Balance Models for Vertical Gas-Liquid Subcooled Boiling Flow of First Loop of Nuclear Power Plant

Ejemplares similares