A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods.
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| Title: | A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods. |
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| Authors: | Krupkin, A. V.1 (AUTHOR) avkrupkin@bochvar.ru, Kuznetsov, V. I.1 (AUTHOR), Loktaev, K. V.1 (AUTHOR), Novikov, V. V.1 (AUTHOR) |
| Source: | Atomic Energy. Jan2025, Vol. 136 Issue 1/2, p50-56. 7p. |
| Subjects: | Wood pellets, Geothermal reactors, Fission products, Fracture mechanics, Nuclear fuel rods, Stress corrosion cracking |
| Abstract: | An increase in power during transient operating modes of reactors can lead to the depressurization of fuel rods due to the stress corrosion cracking mechanism. Expansion of fuel pellets due to increasing power induces tensile stresses in the cladding, which can initiate the formation and growth of corrosion cracks in the presence of aggressive fission products. Therefore, the plotted limit curve is primarily aimed at preventing circumferential stresses in the cladding from exceeding a certain maximum value during abrupt changes in power. The present article describes a system for performing multivariate statistical calculations of a single power increase to plot an envelope curve for the permissible area of fuel rod operation. The system uses the START-3A code to perform fuel rod calculations, which includes the ability to vary model and design parameters. The methodology for the calculated limit curve for a rapid increase in the power of a VVER-1200 reactor is presented with examples. [ABSTRACT FROM AUTHOR] |
| Copyright of Atomic Energy is the property of Springer Nature 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 |
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| Header | DbId: egs DbLabel: Engineering Source An: 181515635 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Krupkin%2C+A%2E+V%2E%22">Krupkin, A. V.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> avkrupkin@bochvar.ru</i><br /><searchLink fieldCode="AR" term="%22Kuznetsov%2C+V%2E+I%2E%22">Kuznetsov, V. I.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Loktaev%2C+K%2E+V%2E%22">Loktaev, K. V.</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Novikov%2C+V%2E+V%2E%22">Novikov, V. V.</searchLink><relatesTo>1</relatesTo> (AUTHOR) – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Atomic+Energy%22">Atomic Energy</searchLink>. Jan2025, Vol. 136 Issue 1/2, p50-56. 7p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Wood+pellets%22">Wood pellets</searchLink><br /><searchLink fieldCode="DE" term="%22Geothermal+reactors%22">Geothermal reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Fission+products%22">Fission products</searchLink><br /><searchLink fieldCode="DE" term="%22Fracture+mechanics%22">Fracture mechanics</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+fuel+rods%22">Nuclear fuel rods</searchLink><br /><searchLink fieldCode="DE" term="%22Stress+corrosion+cracking%22">Stress corrosion cracking</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: An increase in power during transient operating modes of reactors can lead to the depressurization of fuel rods due to the stress corrosion cracking mechanism. Expansion of fuel pellets due to increasing power induces tensile stresses in the cladding, which can initiate the formation and growth of corrosion cracks in the presence of aggressive fission products. Therefore, the plotted limit curve is primarily aimed at preventing circumferential stresses in the cladding from exceeding a certain maximum value during abrupt changes in power. The present article describes a system for performing multivariate statistical calculations of a single power increase to plot an envelope curve for the permissible area of fuel rod operation. The system uses the START-3A code to perform fuel rod calculations, which includes the ability to vary model and design parameters. The methodology for the calculated limit curve for a rapid increase in the power of a VVER-1200 reactor is presented with examples. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Atomic Energy is the property of Springer Nature 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: 10.1007/s10512-024-01129-0 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 7 StartPage: 50 Subjects: – SubjectFull: Wood pellets Type: general – SubjectFull: Geothermal reactors Type: general – SubjectFull: Fission products Type: general – SubjectFull: Fracture mechanics Type: general – SubjectFull: Nuclear fuel rods Type: general – SubjectFull: Stress corrosion cracking Type: general Titles: – TitleFull: A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Krupkin, A. V. – PersonEntity: Name: NameFull: Kuznetsov, V. I. – PersonEntity: Name: NameFull: Loktaev, K. V. – PersonEntity: Name: NameFull: Novikov, V. V. IsPartOfRelationships: – BibEntity: Dates: – D: 01 M: 01 Text: Jan2025 Type: published Y: 2025 Identifiers: – Type: issn-print Value: 10634258 Numbering: – Type: volume Value: 136 – Type: issue Value: 1/2 Titles: – TitleFull: Atomic Energy Type: main |
| ResultId | 1 |
