Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break

For the structural integrity evaluation of pressurized water reactor (PWR) steam generator (SG) tubes subjected to transient hydraulic loading, determination of the tube-to-tube gap velocity and static pressure distributions along the tubes is prerequisite. This paper addresses both computational fl...

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Main Authors: Jong Chull Jo, Jae-Jun Jeong, Frederick J. Moody
Format: Article
Language:English
Published: Elsevier 2021-03-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320308597
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spelling doaj-510a7f033bab458c993f01340478a0ae2021-03-03T04:20:57ZengElsevierNuclear Engineering and Technology1738-57332021-03-0153310291040Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line breakJong Chull Jo0Jae-Jun Jeong1Frederick J. Moody2Korea Institute of Nuclear Safety, Yusung-gu, Daejon, 34142, South Korea; Pusan National University, School of Mechanical Engineering, Geumjeong-gu, Busan, 46241, South Korea; Corresponding author. Pusan National University, School of Mechanical Engineering, Geumjeong-gu, Busan, 46241, South Korea. Tel.: 042 868 0231, (051) 510 2782.Pusan National University, School of Mechanical Engineering, Geumjeong-gu, Busan, 46241, South Korea2125 N. Olive Ave. APT D 33, Turlock, CA, 95382-1936, USAFor the structural integrity evaluation of pressurized water reactor (PWR) steam generator (SG) tubes subjected to transient hydraulic loading, determination of the tube-to-tube gap velocity and static pressure distributions along the tubes is prerequisite. This paper addresses both computational fluid dynamics (CFD) and analytical approaches for predicting the tube-to-tube gap velocity and static pressure distributions during blowdown following a feedwater line break (FWLB) accident at a PWR SG. First of all, a comparative study on CFD calculations of the transient velocity and pressure distributions in the SG secondary sides for two different models having 30 or no tubes is performed. The result shows that the velocities of sub-cooled water flowing between any adjacent two tubes of a tubed SG model during blowdown can be roughly estimated by applying the specified SG secondary side porosity to those of the no-tubed SG model. Secondly, simplified analytical approximate solutions for the steady two-dimensional SG secondary flow velocity and pressure distributions under a given discharge flowrate are derived using a line sink model. The simplified analytical solutions are validated by comparing them to the CFD calculations.http://www.sciencedirect.com/science/article/pii/S1738573320308597Feedwater line breakBlowdownNumerical predictionAnalytical approximationSteam generator flow field
collection DOAJ
language English
format Article
sources DOAJ
author Jong Chull Jo
Jae-Jun Jeong
Frederick J. Moody
spellingShingle Jong Chull Jo
Jae-Jun Jeong
Frederick J. Moody
Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
Nuclear Engineering and Technology
Feedwater line break
Blowdown
Numerical prediction
Analytical approximation
Steam generator flow field
author_facet Jong Chull Jo
Jae-Jun Jeong
Frederick J. Moody
author_sort Jong Chull Jo
title Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
title_short Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
title_full Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
title_fullStr Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
title_full_unstemmed Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
title_sort numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-03-01
description For the structural integrity evaluation of pressurized water reactor (PWR) steam generator (SG) tubes subjected to transient hydraulic loading, determination of the tube-to-tube gap velocity and static pressure distributions along the tubes is prerequisite. This paper addresses both computational fluid dynamics (CFD) and analytical approaches for predicting the tube-to-tube gap velocity and static pressure distributions during blowdown following a feedwater line break (FWLB) accident at a PWR SG. First of all, a comparative study on CFD calculations of the transient velocity and pressure distributions in the SG secondary sides for two different models having 30 or no tubes is performed. The result shows that the velocities of sub-cooled water flowing between any adjacent two tubes of a tubed SG model during blowdown can be roughly estimated by applying the specified SG secondary side porosity to those of the no-tubed SG model. Secondly, simplified analytical approximate solutions for the steady two-dimensional SG secondary flow velocity and pressure distributions under a given discharge flowrate are derived using a line sink model. The simplified analytical solutions are validated by comparing them to the CFD calculations.
topic Feedwater line break
Blowdown
Numerical prediction
Analytical approximation
Steam generator flow field
url http://www.sciencedirect.com/science/article/pii/S1738573320308597
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