Development of TSAC1.0 and application to reactivity insertion accident of CARR
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| Title: | Development of TSAC1.0 and application to reactivity insertion accident of CARR |
|---|---|
| Authors: | Chen, Ronghua1, Su, G.H.1 ghsu@mail.xjtu.edu.cn, Tian, Wenxi wxtian@mail.xjtu.edu.cn, Qiu, Suizheng1, Jia, Dounan1 |
| Source: | Progress in Nuclear Energy. Jan2011, Vol. 53 Issue 1, p1-9. 9p. |
| Subjects: | Nuclear reactor reactivity, Nuclear reactor accidents, Hydraulic engineering, Nuclear reactor safety measures, Nuclear engineering, Simulation methods & models, Temperature effect, Transients (Dynamics) |
| Abstract: | Abstract: In this study, we have developed a thermo-hydraulic and safety analysis code named TSAC1.0 with Visual Fortran 6.5 to analyze the thermal-hydraulic characteristics of the China advanced research reactor (CARR) under reactivity insertion accident (RIA) which was induced by unexpected control rod withdrawal in full power condition. The neutron kinetic model depended on the point kinetics with six groups of delayed neutrons including reactivity feedback effects and it was adopted for the solution of reactor power. Furthermore, a new simple and convenient model was adopted for the solution of the transient behaviors of main pump instead of the complicated four-quadrant model. Visual input, real-time processing and dynamic visualization output were achieved using Microsoft Visual Studio.NET 2003 to make the application of TSAC1.0 much more convenient in the engineering. The simulated results of TSAC1.0 were found to be in reasonable agreement with those of RELAP5/MOD3 and showed that the parameters, including the peak coolant temperature, the peak heat structure temperature, and MDNBR, were in the acceptable range of design safety limit under RIA. [ABSTRACT FROM AUTHOR] |
| Copyright of Progress in Nuclear Energy 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 |
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| Header | DbId: egs DbLabel: Engineering Source An: 55211521 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Development of TSAC1.0 and application to reactivity insertion accident of CARR – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Chen%2C+Ronghua%22">Chen, Ronghua</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Su%2C+G%2EH%2E%22">Su, G.H.</searchLink><relatesTo>1</relatesTo><i> ghsu@mail.xjtu.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Tian%2C+Wenxi%22">Tian, Wenxi</searchLink><i> wxtian@mail.xjtu.edu.cn</i><br /><searchLink fieldCode="AR" term="%22Qiu%2C+Suizheng%22">Qiu, Suizheng</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Jia%2C+Dounan%22">Jia, Dounan</searchLink><relatesTo>1</relatesTo> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Progress+in+Nuclear+Energy%22">Progress in Nuclear Energy</searchLink>. Jan2011, Vol. 53 Issue 1, p1-9. 9p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Nuclear+reactor+reactivity%22">Nuclear reactor reactivity</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+accidents%22">Nuclear reactor accidents</searchLink><br /><searchLink fieldCode="DE" term="%22Hydraulic+engineering%22">Hydraulic engineering</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+safety+measures%22">Nuclear reactor safety measures</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+engineering%22">Nuclear engineering</searchLink><br /><searchLink fieldCode="DE" term="%22Simulation+methods+%26+models%22">Simulation methods & models</searchLink><br /><searchLink fieldCode="DE" term="%22Temperature+effect%22">Temperature effect</searchLink><br /><searchLink fieldCode="DE" term="%22Transients+%28Dynamics%29%22">Transients (Dynamics)</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: Abstract: In this study, we have developed a thermo-hydraulic and safety analysis code named TSAC1.0 with Visual Fortran 6.5 to analyze the thermal-hydraulic characteristics of the China advanced research reactor (CARR) under reactivity insertion accident (RIA) which was induced by unexpected control rod withdrawal in full power condition. The neutron kinetic model depended on the point kinetics with six groups of delayed neutrons including reactivity feedback effects and it was adopted for the solution of reactor power. Furthermore, a new simple and convenient model was adopted for the solution of the transient behaviors of main pump instead of the complicated four-quadrant model. Visual input, real-time processing and dynamic visualization output were achieved using Microsoft Visual Studio.NET 2003 to make the application of TSAC1.0 much more convenient in the engineering. The simulated results of TSAC1.0 were found to be in reasonable agreement with those of RELAP5/MOD3 and showed that the parameters, including the peak coolant temperature, the peak heat structure temperature, and MDNBR, were in the acceptable range of design safety limit under RIA. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Progress in Nuclear Energy 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.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1016/j.pnucene.2010.09.015 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 9 StartPage: 1 Subjects: – SubjectFull: Nuclear reactor reactivity Type: general – SubjectFull: Nuclear reactor accidents Type: general – SubjectFull: Hydraulic engineering Type: general – SubjectFull: Nuclear reactor safety measures Type: general – SubjectFull: Nuclear engineering Type: general – SubjectFull: Simulation methods & models Type: general – SubjectFull: Temperature effect Type: general – SubjectFull: Transients (Dynamics) Type: general Titles: – TitleFull: Development of TSAC1.0 and application to reactivity insertion accident of CARR Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Chen, Ronghua – PersonEntity: Name: NameFull: Su, G.H. – PersonEntity: Name: NameFull: Tian, Wenxi – PersonEntity: Name: NameFull: Qiu, Suizheng – PersonEntity: Name: NameFull: Jia, Dounan IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 01 Text: Jan2011 Type: published Y: 2011 Identifiers: – Type: issn-print Value: 01491970 Numbering: – Type: volume Value: 53 – Type: issue Value: 1 Titles: – TitleFull: Progress in Nuclear Energy Type: main |
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