Changes in the Structure and Mechanical Properties of the SAV-1 Alloy and Structural Fe-Cr-Ni Steels After Long-Term Service as Core Materials in Nuclear Reactors.
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| Title: | Changes in the Structure and Mechanical Properties of the SAV-1 Alloy and Structural Fe-Cr-Ni Steels After Long-Term Service as Core Materials in Nuclear Reactors. |
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| Authors: | Dikov, Alexey1 (AUTHOR), Kislitsin, Sergey1 (AUTHOR) skislitsin@inp.kz, Ivanov, Boris1 (AUTHOR), Kiryanov, Ruslan1 (AUTHOR), Maksimkin, Egor1 (AUTHOR) |
| Source: | Materials (1996-1944). Jul2025, Vol. 18 Issue 14, p3391. 15p. |
| Subjects: | Nuclear reactors, Core materials, Mechanical behavior of materials, Fast reactors, Irradiation, Alloys, Durability |
| Abstract: | This article presents the results of studies of the degradation of the structure and mechanical properties of the core materials BN-350 fast neutron and research WWR-K reactors required to justify the service life extension of early-generation power and research reactors. Extending the service life of nuclear reactors is a modern problem, since most operating reactors are early-generation reactors that have exhausted their design lifespan. The possibility of extending the service life is largely determined by the condition of the structural materials of the nuclear facility, i.e., their residual resources must ensure safe operation of the reactor. For the SAV-1 alloy, the structural material of the WWR-K reactor, studies were conducted on witness samples which were in the active zone during its operation for 56 years. It was found that yield strength and tensile strength of the irradiated SAV-1 alloy decreased by 24–48%, and relative elongation decreased by ~2% compared to the unirradiated alloy. Inside the grains and along their boundaries, there were particles of secondary phases enriched with silicon, which is typical for aged aluminum alloys. For irradiated structural steels of power reactors, studied at 350–450 C, hardening and a damping nature of creep were revealed, caused by dispersion hardening and the Hall–Petch effect. [ABSTRACT FROM AUTHOR] |
| Copyright of Materials (1996-1944) is the property of MDPI 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.) | |
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| Header | DbId: egs DbLabel: Engineering Source An: 186929200 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Changes in the Structure and Mechanical Properties of the SAV-1 Alloy and Structural Fe-Cr-Ni Steels After Long-Term Service as Core Materials in Nuclear Reactors. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Dikov%2C+Alexey%22">Dikov, Alexey</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Kislitsin%2C+Sergey%22">Kislitsin, Sergey</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> skislitsin@inp.kz</i><br /><searchLink fieldCode="AR" term="%22Ivanov%2C+Boris%22">Ivanov, Boris</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Kiryanov%2C+Ruslan%22">Kiryanov, Ruslan</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Maksimkin%2C+Egor%22">Maksimkin, Egor</searchLink><relatesTo>1</relatesTo> (AUTHOR) – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Materials+%281996-1944%29%22">Materials (1996-1944)</searchLink>. Jul2025, Vol. 18 Issue 14, p3391. 15p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Core+materials%22">Core materials</searchLink><br /><searchLink fieldCode="DE" term="%22Mechanical+behavior+of+materials%22">Mechanical behavior of materials</searchLink><br /><searchLink fieldCode="DE" term="%22Fast+reactors%22">Fast reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Irradiation%22">Irradiation</searchLink><br /><searchLink fieldCode="DE" term="%22Alloys%22">Alloys</searchLink><br /><searchLink fieldCode="DE" term="%22Durability%22">Durability</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: This article presents the results of studies of the degradation of the structure and mechanical properties of the core materials BN-350 fast neutron and research WWR-K reactors required to justify the service life extension of early-generation power and research reactors. Extending the service life of nuclear reactors is a modern problem, since most operating reactors are early-generation reactors that have exhausted their design lifespan. The possibility of extending the service life is largely determined by the condition of the structural materials of the nuclear facility, i.e., their residual resources must ensure safe operation of the reactor. For the SAV-1 alloy, the structural material of the WWR-K reactor, studies were conducted on witness samples which were in the active zone during its operation for 56 years. It was found that yield strength and tensile strength of the irradiated SAV-1 alloy decreased by 24–48%, and relative elongation decreased by ~2% compared to the unirradiated alloy. Inside the grains and along their boundaries, there were particles of secondary phases enriched with silicon, which is typical for aged aluminum alloys. For irradiated structural steels of power reactors, studied at 350–450 C, hardening and a damping nature of creep were revealed, caused by dispersion hardening and the Hall–Petch effect. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Materials (1996-1944) is the property of MDPI 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: 10.3390/ma18143391 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 15 StartPage: 3391 Subjects: – SubjectFull: Nuclear reactors Type: general – SubjectFull: Core materials Type: general – SubjectFull: Mechanical behavior of materials Type: general – SubjectFull: Fast reactors Type: general – SubjectFull: Irradiation Type: general – SubjectFull: Alloys Type: general – SubjectFull: Durability Type: general Titles: – TitleFull: Changes in the Structure and Mechanical Properties of the SAV-1 Alloy and Structural Fe-Cr-Ni Steels After Long-Term Service as Core Materials in Nuclear Reactors. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Dikov, Alexey – PersonEntity: Name: NameFull: Kislitsin, Sergey – PersonEntity: Name: NameFull: Ivanov, Boris – PersonEntity: Name: NameFull: Kiryanov, Ruslan – PersonEntity: Name: NameFull: Maksimkin, Egor IsPartOfRelationships: – BibEntity: Dates: – D: 15 M: 07 Text: Jul2025 Type: published Y: 2025 Identifiers: – Type: issn-print Value: 19961944 Numbering: – Type: volume Value: 18 – Type: issue Value: 14 Titles: – TitleFull: Materials (1996-1944) Type: main |
| ResultId | 1 |
