Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition

In nuclear engineering, the occurrence of critical heat flux (CHF) is complicated for rod bundle, and it is much more difficult to predict the CHF when it is in natural circulation under motion condition. In this paper, the dryout-type CHF is investigated for the rod bundle in a natural circulation...

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Main Authors: Siyang Huang, Wenxi Tian, Xiaoyang Wang, Ronghua Chen, Nina Yue, Mengmeng Xi, G.H. Su, Suizheng Qiu
Format: Article
Language:English
Published: Elsevier 2020-04-01
Series:Nuclear Engineering and Technology
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319303924
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spelling doaj-745d334c695d4718a0a6a390279c1aa32020-11-25T02:59:23ZengElsevierNuclear Engineering and Technology1738-57332020-04-01524721733Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion conditionSiyang Huang0Wenxi Tian1Xiaoyang Wang2Ronghua Chen3Nina Yue4Mengmeng Xi5G.H. Su6Suizheng Qiu7Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, ChinaShaanxi Key Lab. of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, ChinaWuhan Second Ship Design and Research Institute, Wuhan, 430205, ChinaShaanxi Key Lab. of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, ChinaCNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, ChinaCNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, ChinaShaanxi Key Lab. of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, ChinaIn nuclear engineering, the occurrence of critical heat flux (CHF) is complicated for rod bundle, and it is much more difficult to predict the CHF when it is in natural circulation under motion condition. In this paper, the dryout-type CHF is investigated for the rod bundle in a natural circulation loop under rolling motion condition based on the coupled analysis of subchannel method, a one-dimensional system analysis method and a CHF mechanism model, namely the three-fluid model for annular flow. In order to consider the rolling effect of the natural circulation loop, the subchannel model is connected to the one-dimensional system code at the inlet and outlet of the rod bundle. The subchannel analysis provides the local thermal hydraulic parameters as input for the CHF mechanism model to calculate the occurrence of CHF. The rolling motion is modeled by additional motion forces in the momentum equation. First, the calculation methods of the natural circulation and CHF are validated by a published natural circulation experiment data and a CHF empirical correlation, respectively. Then, the CHF of the rod bundle in a natural circulation loop under both the stationary and rolling motion condition is predicted and analyzed. According to the calculation results, CHF under stationary condition is smaller than that under rolling motion condition. Besides, the CHF decreases with the increase of the rolling period and angular acceleration amplitude within the range of inlet subcooling and mass flux adopted in the current research. This paper can provide useful information for the prediction of CHF in natural circulation under motion condition, which is important for the nuclear reactor design improvement and safety analysis. Keywords: Dryout CHF, Natural circulation, Motion conditionhttp://www.sciencedirect.com/science/article/pii/S1738573319303924
collection DOAJ
language English
format Article
sources DOAJ
author Siyang Huang
Wenxi Tian
Xiaoyang Wang
Ronghua Chen
Nina Yue
Mengmeng Xi
G.H. Su
Suizheng Qiu
spellingShingle Siyang Huang
Wenxi Tian
Xiaoyang Wang
Ronghua Chen
Nina Yue
Mengmeng Xi
G.H. Su
Suizheng Qiu
Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
Nuclear Engineering and Technology
author_facet Siyang Huang
Wenxi Tian
Xiaoyang Wang
Ronghua Chen
Nina Yue
Mengmeng Xi
G.H. Su
Suizheng Qiu
author_sort Siyang Huang
title Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
title_short Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
title_full Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
title_fullStr Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
title_full_unstemmed Prediction of dryout-type CHF for rod bundle in natural circulation loop under motion condition
title_sort prediction of dryout-type chf for rod bundle in natural circulation loop under motion condition
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2020-04-01
description In nuclear engineering, the occurrence of critical heat flux (CHF) is complicated for rod bundle, and it is much more difficult to predict the CHF when it is in natural circulation under motion condition. In this paper, the dryout-type CHF is investigated for the rod bundle in a natural circulation loop under rolling motion condition based on the coupled analysis of subchannel method, a one-dimensional system analysis method and a CHF mechanism model, namely the three-fluid model for annular flow. In order to consider the rolling effect of the natural circulation loop, the subchannel model is connected to the one-dimensional system code at the inlet and outlet of the rod bundle. The subchannel analysis provides the local thermal hydraulic parameters as input for the CHF mechanism model to calculate the occurrence of CHF. The rolling motion is modeled by additional motion forces in the momentum equation. First, the calculation methods of the natural circulation and CHF are validated by a published natural circulation experiment data and a CHF empirical correlation, respectively. Then, the CHF of the rod bundle in a natural circulation loop under both the stationary and rolling motion condition is predicted and analyzed. According to the calculation results, CHF under stationary condition is smaller than that under rolling motion condition. Besides, the CHF decreases with the increase of the rolling period and angular acceleration amplitude within the range of inlet subcooling and mass flux adopted in the current research. This paper can provide useful information for the prediction of CHF in natural circulation under motion condition, which is important for the nuclear reactor design improvement and safety analysis. Keywords: Dryout CHF, Natural circulation, Motion condition
url http://www.sciencedirect.com/science/article/pii/S1738573319303924
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