Evolution of Microstructure and Surface Characteristics of FeCrAl alloys when Subjected to Flow Boiling Testing

Umretiya, Rajnikant V.; Lee, Donghwi; Elward, Barret; Anderson, Mark; Rebak, Raul B.; Rojas, Jessika V.

doi:10.1016/j.jnucmat.2021.153269

Title: Evolution of Microstructure and Surface Characteristics of FeCrAl alloys when Subjected to Flow Boiling Testing

Journal Article · 08 September 2021 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2021.153269 · OSTI ID:1977373

Umretiya, Rajnikant V. ^[1]; Lee, Donghwi ^[2]; Elward, Barret ^[2]; Anderson, Mark ^[2]; Rebak, Raul B. ^[3]; Rojas, Jessika V. ^[4]

Virginia Commonwealth Univ., Richmond, VA (United States); OSTI
Univ. of Wisconsin, Madison, WI (United States)
General Electric Research, Schenectady, NY (United States)
Virginia Commonwealth Univ., Richmond, VA (United States)

FeCrAl alloys are candidate materials for manufacturing accident-tolerant fuel (ATF) cladding intended for light water reactors to increase fuel reliability and safety during design-basis and beyond-design-basis accident scenarios. The evolution of the materials' surface characteristics, microstructure, and mechanical properties when exposed to the Critical Heat Flux (CHF) in flow boiling testing is crucial for safety analysis while providing insights into their thermal-hydraulic performance in nuclear reactors. After CHF, the surface chemistry of two FeCrAl alloys, APMT and C26M, was studied to understand their evolution at the early stage of high-temperature excursions in short time periods. The results indicated a thin layer composed of oxides and hydroxides of Al, Cr, and Fe with varying proportions at different depths in the layer, as indicated by X-ray photoelectron spectroscopy (XPS) and depth profiling. The cross-sections prepared by focused ion beam (FIB) revealed the growth of an oxide layer, in the range of 90-180 nm thick, on the alloys' surfaces. The evolution of the materials' surface chemistry also led to a noticeable post CHF excursion increase in their wettability, with a slight increase in roughness. Further, the investigation of the materials' mechanical properties indicated a modest increase in hardness by 10-15% as well as an increase in their yield strength, as evidenced by the microindentation and ring compression tests conducted before and after CHF testing. Scanning electron Microscopy (SEM) and X-ray diffraction (XRD) were used to investigate microstructural features of the materials and their changes after CHF treatment.

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Research Organization:: Virginia Commonwealth Univ., Richmond, VA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: NE0008709

OSTI ID:: 1977373

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 557; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Title: Evolution of Microstructure and Surface Characteristics of FeCrAl alloys when Subjected to Flow Boiling Testing

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