View in EDS

Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor

Saved in:
Bibliographic Details
Title: Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor
Authors: Wu, Y.W.1, Su, G.H. ghsu@mail.xjtu.edu.cn, Qiu, S.Z.1, Zhuang, C.J.1
Source: Nuclear Engineering & Design. Jan2010, Vol. 240 Issue 1, p112-122. 11p.
Subjects: Computer software, Thermodynamics, Pressurized water reactors, Neutrons, Steam generators, Transients (Dynamics), FORTRAN, Nuclear reactor accidents
Geographic Terms: China
Abstract: Abstract: A point reactor neutron kinetics model, a drift-flow U-tube steam generator model, a non-equilibrium three-region pressurizer model and other models were established and a transient analysis code with Visual Fortran 6.5 has been developed to analyze the thermal-hydraulic characteristics of the Chinese advanced pressurized water reactor (AC-600). Visual input, real-time processing and dynamic visualization output were achieved with Microsoft Visual Studio.NET 2003, which greatly facilitate applications in the engineering. The software were applied to analyze the transient thermal-hydraulic characteristics of the loss of feed-water accident, the double loops loss-of-flow accident, the reactivity insertion accident, the sudden increase of feed-water temperature accident and the loss of offsite power accident for the Qinshan nuclear power plant in China. The obtained analysis results are significant to the improvement of design and safety operation of the plant. [Copyright &y& Elsevier]
Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
FullText Text:
  Availability: 0
Header DbId: egs
DbLabel: Engineering Source
An: 46752829
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
IllustrationInfo
Items – Name: Title
  Label: Title
  Group: Ti
  Data: Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor
– Name: Author
  Label: Authors
  Group: Au
  Data: <searchLink fieldCode="AR" term="%22Wu%2C+Y%2EW%2E%22">Wu, Y.W.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Su%2C+G%2EH%2E%22">Su, G.H.</searchLink><i> ghsu@mail.xjtu.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Qiu%2C+S%2EZ%2E%22">Qiu, S.Z.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Zhuang%2C+C%2EJ%2E%22">Zhuang, C.J.</searchLink><relatesTo>1</relatesTo>
– Name: TitleSource
  Label: Source
  Group: Src
  Data: <searchLink fieldCode="JN" term="%22Nuclear+Engineering+%26+Design%22">Nuclear Engineering & Design</searchLink>. Jan2010, Vol. 240 Issue 1, p112-122. 11p.
– Name: Subject
  Label: Subjects
  Group: Su
  Data: <searchLink fieldCode="DE" term="%22Computer+software%22">Computer software</searchLink><br /><searchLink fieldCode="DE" term="%22Thermodynamics%22">Thermodynamics</searchLink><br /><searchLink fieldCode="DE" term="%22Pressurized+water+reactors%22">Pressurized water reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Neutrons%22">Neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Steam+generators%22">Steam generators</searchLink><br /><searchLink fieldCode="DE" term="%22Transients+%28Dynamics%29%22">Transients (Dynamics)</searchLink><br /><searchLink fieldCode="DE" term="%22FORTRAN%22">FORTRAN</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+accidents%22">Nuclear reactor accidents</searchLink>
– Name: SubjectGeographic
  Label: Geographic Terms
  Group: Su
  Data: <searchLink fieldCode="DE" term="%22China%22">China</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: Abstract: A point reactor neutron kinetics model, a drift-flow U-tube steam generator model, a non-equilibrium three-region pressurizer model and other models were established and a transient analysis code with Visual Fortran 6.5 has been developed to analyze the thermal-hydraulic characteristics of the Chinese advanced pressurized water reactor (AC-600). Visual input, real-time processing and dynamic visualization output were achieved with Microsoft Visual Studio.NET 2003, which greatly facilitate applications in the engineering. The software were applied to analyze the transient thermal-hydraulic characteristics of the loss of feed-water accident, the double loops loss-of-flow accident, the reactivity insertion accident, the sudden increase of feed-water temperature accident and the loss of offsite power accident for the Qinshan nuclear power plant in China. The obtained analysis results are significant to the improvement of design and safety operation of the plant. [Copyright &y& Elsevier]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Nuclear Engineering & Design is the property of Elsevier B.V. and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=egs&AN=46752829
RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1016/j.nucengdes.2009.10.020
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 11
        StartPage: 112
    Subjects:
      – SubjectFull: Computer software
        Type: general
      – SubjectFull: Thermodynamics
        Type: general
      – SubjectFull: Pressurized water reactors
        Type: general
      – SubjectFull: Neutrons
        Type: general
      – SubjectFull: Steam generators
        Type: general
      – SubjectFull: Transients (Dynamics)
        Type: general
      – SubjectFull: FORTRAN
        Type: general
      – SubjectFull: Nuclear reactor accidents
        Type: general
      – SubjectFull: China
        Type: general
    Titles:
      – TitleFull: Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor
        Type: main
  BibRelationships:
    HasContributorRelationships:
      – PersonEntity:
          Name:
            NameFull: Wu, Y.W.
      – PersonEntity:
          Name:
            NameFull: Su, G.H.
      – PersonEntity:
          Name:
            NameFull: Qiu, S.Z.
      – PersonEntity:
          Name:
            NameFull: Zhuang, C.J.
    IsPartOfRelationships:
      – BibEntity:
          Dates:
            – D: 01
              M: 01
              Text: Jan2010
              Type: published
              Y: 2010
          Identifiers:
            – Type: issn-print
              Value: 00295493
          Numbering:
            – Type: volume
              Value: 240
            – Type: issue
              Value: 1
          Titles:
            – TitleFull: Nuclear Engineering & Design
              Type: main
ResultId 1