Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments

Rod bundle experiments with axially uniform and nonuniform heat fluxes are examined to explore the potential limitations of using uniform rod bundle CHF data for CHF correlation development of light water reactors with nonuniform axial power distribution (APD). The case of upstream burnout is presen...

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Main Authors: Baowen Yang, Jianqiang Shan, Junli Gou, Hui Zhang, Aiguo Liu, Hu Mao
Format: Article
Language:English
Published: Wiley 2014-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2014/462460
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author Baowen Yang
Jianqiang Shan
Junli Gou
Hui Zhang
Aiguo Liu
Hu Mao
author_facet Baowen Yang
Jianqiang Shan
Junli Gou
Hui Zhang
Aiguo Liu
Hu Mao
author_sort Baowen Yang
collection DOAJ
description Rod bundle experiments with axially uniform and nonuniform heat fluxes are examined to explore the potential limitations of using uniform rod bundle CHF data for CHF correlation development of light water reactors with nonuniform axial power distribution (APD). The case of upstream burnout is presented as an example of unique phenomena associated with nonuniform rod bundle CHF experiments. It is a result from combined effect of axial nonuniform power shape and different interchannel mixing mechanisms. In addition, several key parameters are investigated with respect to their potential impacts on the thermal-hydraulic behaviors between rod bundles with uniform and nonuniform APDs. This type of misrepresentation cannot be amended or compensated through the use of correction factors due to the lack of critical information in the uniform rod bundle CHF testing as well as the fundamental difference in the underlining driving mechanisms. Other potential issues involved with the use of uniform rod bundle CHF data for nonuniform APD system applications also present strong evidence concerning the limitations and inadequacy of using uniform rod bundle CHF data for the correlation, prediction, and design limit calculation for safety analysis.
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institution Kabale University
issn 1687-6075
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publishDate 2014-01-01
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series Science and Technology of Nuclear Installations
spelling doaj-art-dd46fdf413f24662b7c712482b782f652025-02-03T05:53:19ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832014-01-01201410.1155/2014/462460462460Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF ExperimentsBaowen Yang0Jianqiang Shan1Junli Gou2Hui Zhang3Aiguo Liu4Hu Mao5Science and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaScience and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaScience and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaScience and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaScience and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaScience and Technology Center for Advanced Fuel Research & Development, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, ChinaRod bundle experiments with axially uniform and nonuniform heat fluxes are examined to explore the potential limitations of using uniform rod bundle CHF data for CHF correlation development of light water reactors with nonuniform axial power distribution (APD). The case of upstream burnout is presented as an example of unique phenomena associated with nonuniform rod bundle CHF experiments. It is a result from combined effect of axial nonuniform power shape and different interchannel mixing mechanisms. In addition, several key parameters are investigated with respect to their potential impacts on the thermal-hydraulic behaviors between rod bundles with uniform and nonuniform APDs. This type of misrepresentation cannot be amended or compensated through the use of correction factors due to the lack of critical information in the uniform rod bundle CHF testing as well as the fundamental difference in the underlining driving mechanisms. Other potential issues involved with the use of uniform rod bundle CHF data for nonuniform APD system applications also present strong evidence concerning the limitations and inadequacy of using uniform rod bundle CHF data for the correlation, prediction, and design limit calculation for safety analysis.http://dx.doi.org/10.1155/2014/462460
spellingShingle Baowen Yang
Jianqiang Shan
Junli Gou
Hui Zhang
Aiguo Liu
Hu Mao
Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
Science and Technology of Nuclear Installations
title Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
title_full Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
title_fullStr Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
title_full_unstemmed Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
title_short Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
title_sort uniform versus nonuniform axial power distribution in rod bundle chf experiments
url http://dx.doi.org/10.1155/2014/462460
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AT junligou uniformversusnonuniformaxialpowerdistributioninrodbundlechfexperiments
AT huizhang uniformversusnonuniformaxialpowerdistributioninrodbundlechfexperiments
AT aiguoliu uniformversusnonuniformaxialpowerdistributioninrodbundlechfexperiments
AT humao uniformversusnonuniformaxialpowerdistributioninrodbundlechfexperiments