HARDENING BEHAVIOR OF NUCLEAR STRUCTURAL MATERIALS UNDER ION IRRADIATION

The evaluation of irradiation hardening and embrittlement is critically important for the development of next generation nuclear structural materials tolerant to neutron irradiation. This review summarizes research progress on experimental observations aimed at elucidating the mechanisms of radiation induced hardening in ion irradiated materials, focusing on the correlation between irradiation effects and mechanical property changes. We present the basic information for the application of ion irradiation and nanoindentation techniques to characterize the mechanical properties of nuclear structural materials. The effects of irradiation on advanced structural materials, including oxide dispersion strengthened (ODS) austenitic steels, ferritic martensitic steels, and high entropy alloys, are analyzed. The dependence of hardening parameters on the irradiation dose and their relationship with microstructural evolution are examined. Findings indicate that these advanced alloys exhibit reduced susceptibility to irradiation induced hardening compared to conventional austenitic stainless steels.

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Published
2024-08-19
DOI
https://doi.org/10.46813/2024-152-003
Primary Topic
Fusion materials and technologies
Type
article
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article

HARDENING BEHAVIOR OF NUCLEAR STRUCTURAL MATERIALS UNDER ION IRRADIATION

G.D. Tolstolutska, M.O. Azarenkov, S.A. Karpov
Fusion materials and technologies
article

HARDENING BEHAVIOR OF NUCLEAR STRUCTURAL MATERIALS UNDER ION IRRADIATION

G.D. Tolstolutska, M.O. Azarenkov, S.A. Karpov
article en

Abstract

The evaluation of irradiation hardening and embrittlement is critically important for the development of next generation nuclear structural materials tolerant to neutron irradiation. This review summarizes research progress on experimental observations aimed at elucidating the mechanisms of radiation induced hardening in ion irradiated materials, focusing on the correlation between irradiation effects and mechanical property changes. We present the basic information for the application of ion irradiation and nanoindentation techniques to characterize the mechanical properties of nuclear structural materials. The effects of irradiation on advanced structural materials, including oxide dispersion strengthened (ODS) austenitic steels, ferritic martensitic steels, and high entropy alloys, are analyzed. The dependence of hardening parameters on the irradiation dose and their relationship with microstructural evolution are examined. Findings indicate that these advanced alloys exhibit reduced susceptibility to irradiation induced hardening compared to conventional austenitic stainless steels.

Kharkiv Institute of Physics and Technology (UA)
Openalex Percentile: Top 92%
Fusion materials and technologies
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