Impact of added Inconel and stainless steel on zirconium-based alloys for nuclear waste applications

Gattu, V. K.; Han, Sehee; Chen, X.; Park, H. S.; Ebert, W. L.; Indacochea, J. E.

doi:10.1080/1478422x.2022.2058779

Cited by 1 publication

(4 citation statements)

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“… 29 Corrosion resistance of SS 304L, Inconel 718, and trim chromium was studied under acidic and alkaline electrolytes conditions. 30 The microstructural characterization and potentiodynamic (PD) parameters of these alloys were evaluated. Surface analysis of the corroded alloys after potentiodynamic studies clearly revealed that the intermetallics dominated with iron metal and nickel and copper were found relatively low in the presence of Cl – solution.…”

Section: Resultsmentioning

confidence: 99%

“…Surface analysis of the corroded alloys after potentiodynamic studies clearly revealed that the intermetallics dominated with iron metal and nickel and copper were found relatively low in the presence of Cl – solution. 30 Recently, long-term corrosion of multiphase alloy and oxide material were examined under geologic disposal conditions. 31 They confirmed that electrochemical impedance spectroscopy altered the electrical properties of the alloys surfaces and corrosion rates.…”

Section: Resultsmentioning

confidence: 99%

“…From Raman microscopy, X-ray absorption spectroscopy, and synchrotron microfocus X-ray fluorescence, inhomogeneous localization of the uranium element coupled with the oxide layer was observed on the SS surface . Corrosion resistance of SS 304L, Inconel 718, and trim chromium was studied under acidic and alkaline electrolytes conditions . The microstructural characterization and potentiodynamic (PD) parameters of these alloys were evaluated.…”

Section: Resultsmentioning

confidence: 99%

“…The microstructural characterization and potentiodynamic (PD) parameters of these alloys were evaluated. Surface analysis of the corroded alloys after potentiodynamic studies clearly revealed that the intermetallics dominated with iron metal and nickel and copper were found relatively low in the presence of Cl – solution . Recently, long-term corrosion of multiphase alloy and oxide material were examined under geologic disposal conditions .…”

Section: Resultsmentioning

confidence: 99%

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Understanding the Mechanism of Cs Accumulation on Stainless Steel Suspended in Nuclear High-Level Liquid Waste

et al. 2022

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In a nuclear facility, the surface of stainless steels (SS) was found to be contaminated during the processing of radioactive liquid waste. Their safe and secure disposal is highly challenging to the nuclear industry. If the fundamental property of steel corrosion could be evaluated, successful decontamination and effective decommissioning strategies could be planned. Although individual radionuclide contamination behavior on SS metal was studied, till date, SS contamination behavior under the exposure of high-level liquid waste (HLLW) was unexplored. In view of this, investigations were carried out to understand the nature of contamination in SS 304L alloy under the exposure of simulated HLLW (SHLLW). For understanding of radionuclide adsorption behavior on structural materials, scanning electron microscopy/energy dispersive X-ray spectroscopy and X-ray photoelectron spectroscopy have been utilized for SS 304L. The solutions were analyzed using inductively coupled plasma optical emission spectroscopy to calculate the changes in the elemental composition of the solution and corrosion behavior of SS. The passivation of SS coupons was observed in the presence of HNO 3 due to enrichment of Cr at the surface. The deposition of Cs and Mo was noticed, while SS coupons were exposed to SHLLW. At 3 M HNO 3 and room temperature, the SS surface is mildly passivated by Cr enrichment by formation of a Cr oxide layer on the SS surface. However, the passive layer was not thick enough to attenuate the signal from the substrate below the passivated layer. Hence, Fe 0 and Cr 0 were also found along with Cr 3+ and Fe 3+ (in small quantity). When temperature was elevated to 70 °C, the SS surface was completely covered with the Cr oxide layer, and hence no Cr 0 signal was observed. The small signal of Fe 0 indicated that the signal from the substrate surface is present below the passive layer. During the passivation process, Cr diffused toward the passive layer, thereby producing a Cr-depleted layer below the passive layer (Cr 0 signal was not seen). In the case of SHLLW at 70 °C, the surface was fully covered by Cr 3+ , Mo 6+ , and Cs + . Fe and Ni were not observed at all. This finding will help to design an effective corrosion inhibitor and suitable decontamination agent. In addition to that, this information was found to be useful in designing high-performance novel and modern age reactor materials with improved characteristics.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

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