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
Alexey Dikov, Sergey Kislitsin, Boris Ivanov, Ruslan Kiryanov, Egor Maksimkin
TL;DR
This study examines how materials in nuclear reactors degrade over time, affecting their strength and safety for potential service life extension.
Contribution
The study provides new insights into the degradation of SAV-1 alloy and Fe-Cr-Ni steels after long-term reactor operation.
Findings
Irradiated SAV-1 alloy showed decreased yield and tensile strength by 24–48% and reduced elongation.
Secondary silicon-rich phases formed within and along grain boundaries of aged SAV-1 alloy.
Irradiated structural steels exhibited hardening and damping creep due to dispersion and Hall–Petch effects.
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…
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Taxonomy
TopicsNuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering