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Volume 18
Issue 14
10.3390/ma18143391
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Article

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

by
Alexey Dikov
,
Sergey Kislitsin
*,
Boris Ivanov
,
Ruslan Kiryanov
and
Egor Maksimkin
Institute of Nuclear Physics, Ministry of Energy of the Republic of Kazakhstan, Almaty 050032, Kazakhstan
*
Author to whom correspondence should be addressed.
Materials 2025, 18(14), 3391; https://doi.org/10.3390/ma18143391
Submission received: 11 June 2025 / Revised: 9 July 2025 / Accepted: 17 July 2025 / Published: 19 July 2025
(This article belongs to the Section Energy Materials)
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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.
Keywords: core materials; mechanical tests; creep tests; WWR-K reactor; fast neutron BN-350 reactor; neutron irradiation core materials; mechanical tests; creep tests; WWR-K reactor; fast neutron BN-350 reactor; neutron irradiation

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MDPI and ACS Style

Dikov, A.; Kislitsin, S.; Ivanov, B.; Kiryanov, R.; Maksimkin, E. 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. Materials 2025, 18, 3391. https://doi.org/10.3390/ma18143391

AMA Style

Dikov A, Kislitsin S, Ivanov B, Kiryanov R, Maksimkin E. 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. Materials. 2025; 18(14):3391. https://doi.org/10.3390/ma18143391

Chicago/Turabian Style

Dikov, Alexey, Sergey Kislitsin, Boris Ivanov, Ruslan Kiryanov, and Egor Maksimkin. 2025. "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" Materials 18, no. 14: 3391. https://doi.org/10.3390/ma18143391

APA Style

Dikov, A., Kislitsin, S., Ivanov, B., Kiryanov, R., & Maksimkin, E. (2025). 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. Materials, 18(14), 3391. https://doi.org/10.3390/ma18143391

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