Effects of simultaneous proton irradiation on the corrosion of commercial alloys in molten fluoride salt

Almousa, Nouf; Zhou, Weiyue; Woller, K.; Short, Michael P.

doi:10.1016/j.corsci.2023.111154

Cited by 3 publications

(1 citation statement)

References 22 publications

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“…The effect of radiolysis may not be important for molten salts since they consist of dissociated anions and cations. However, acceleration or deceleration of corrosion can occur under proton irradiation in molten salts [57,61], suggesting a dynamic interaction between RIS and the corrosive environment. Regardless the true mechanism(s) of altered corrosion rates, the impact of radiation on corrosive environments is transient and will not exist without radiation during the corrosion process.…”

Section: Corrosion Affected By Radiationmentioning

confidence: 99%

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Jokisaari,

Chen,

Hartmann

et al. 2023

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The Advanced Materials and Manufacturing Technologies (AMMT) program within the Department of Energy, Office of Nuclear Energy (DOE-NE) has developed its current recommendation for its corrosion testing strategy to deploy additively manufactured (AM) materials in advanced nuclear reactors. Additive manufacturing technologies have developed rapidly in recent years, creating new opportunities and challenges for the nuclear industry. To adopt AM technologies, the corrosion performance of AM materials needs to be adequately evaluated.This document is divided into seven chapters designed to support the proposed corrosion research strategy. The strategy focuses on the testing of AM 316H stainless steel (SS) to align with the broader AMMT program. An overview of localized and uniform corrosion mechanisms and their synergy with other degradation modes is provided. Specifically, the corrosion resistance of 316H is largely provided by the presence of an intact chromium oxide film on the surface, and loss or damage of this film is generally responsible for corrosion degradation.Engineering concerns for corrosion behavior are discussed, including component failure mechanisms and corrosion codes and standards. While the standards are extensive, certain material testing standards do not exist that would be relevant for the AMMT program. Reactor-specific corrosion concerns for molten salt reactors, liquid metal-cooled reactors, and high-temperature gas reactors will guide corrosion testing. Key factors likely to influence corrosion properties of AM materials (especially 316H) include build porosity, the presence of unusual phases, residual stress, microsegregation within the cellular substructure, and surface roughness. Post-build treatments and process variability need to be assessed with multiple specimens that are microstructurally quantified to develop structureproperty-performance relationships with uncertainty quantification. Sufficient facilities exist, at least for initial program efforts focusing on characterization of unirradiated material in laboratory settings, across Argonne National Laboratory

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Section: Corrosion Affected By Radiationmentioning

confidence: 99%

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Jokisaari,

Chen,

Hartmann

et al. 2023

View full text Add to dashboard Cite

show abstract

Corrosion testing needs and considerations for additively manufactured materials in nuclear reactors

Jokisaari,

Chen,

Copeland-Johnson

et al. 2024

Progress in Nuclear Energy

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An MeV Proton Irradiation Facility: DICE

Möller,

Höschen,

Arnoldbik

et al. 2024

Materials

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Materials applied in nuclear environments such as fission or fusion power-plants face severe conditions. The irradiation by neutrons induces thermal loads and irradiation damage. Furthermore, coolants in contact with the materials induce corrosion, which is particularly challenging for liquid salts intended for the next generation of fission reactors. A new device (DICE) is installed at the 3.5 MV accelerator at DIFFER for the accelerated testing of such materials under combined irradiation and corrosion conditions. The DICE enables irradiation of samples at temperatures of up to 1050 K and in contact with liquid salts. An integrated shielding and a low power temperature control concept based on radiation cooling enables high-duty cycle application in a standard accelerator laboratory. Ion currents of up to 30 µA are possible with continuous irradiation. This work outlines the technical concept of the device and presents the first data.

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Effects of simultaneous proton irradiation on the corrosion of commercial alloys in molten fluoride salt

Cited by 3 publications

References 22 publications

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Corrosion Testing Needs and Considerations for Additively Manufactured Materials in Nuclear Reactors

Corrosion testing needs and considerations for additively manufactured materials in nuclear reactors

An MeV Proton Irradiation Facility: DICE

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