Mathematical modeling of ozone assisted cerium redox process for the surface removal of stainless steel components using a static mixer as gas-liquid contactor

This paper deals with a cerium based redox chemical process which is used for the surface removal and decontamination of stainless steel components arising from the operation and decommissioning of nuclear facilities. The process involves the corrosion of top contaminated metal surface (∼10–50 μm) by highly oxidizing Ce(IV) ions, in order to remove the entrapped radionuclides . The reduced Ce(III) ions thus generated after the oxidation of metal surface are continuously oxidized back to Ce(IV) by ozone. In this work, a lumped parameter model, accounting for the reduction of Ce(IV) to Ce(III) by steel components and the simultaneous oxidation of Ce(III) to Ce(IV) by ozone in a static mixer , has been developed. The model is experimentally validated by carrying out a corrosion experiment at 5 L scale in ∼0.4 M solution of Ce(IV) in 4 M HNO 3 at room temperature, by using non-radioactive AISI SS304L stainless steel components of different geometries viz. plate, pipe, elbow and T-Joint with a total surface area of 348 cm 2 . Using the validated model, design simulations of a pilot metal decontamination facility are carried out, to illustrate the effect of process parameters on the equilibrium Ce(IV) concentration in the loop, which is critical to component corrosion and decontamination. Simulation results show that, for a given initial cerium salt concentration , increasing the gas/liquid flow rate, ozone concentration, initial nitric acid concentration, and solution volume reduces the rate of fall of equilibrium Ce(IV) concentration with time. However, an increase in the temperature and surface area of the components enhances the rate of fall of equilibrium concentration of Ce(IV) with time. Additionally, reducing acidity of nitric acid has been found to limit the treatment time of components. Furthermore, the choice of a Ce(III) or Ce(IV) salt, as a source of cerium ions, has been shown to have no effect on the corrosion of metal components in a long run, when ozone regeneration of Ce(IV) is employed. Among the components of various geometries, relatively higher corrosion rates have been observed for the components with a curved geometry or a weld joint . SEM images of the welded and non-welded components show the occurrence of intergranular corrosion due to ozonated Ce(IV) solution, which is the likely mechanism for the removal of radionuclides from the metal surface. (Image Resolution: 1197 × 900 pixels). • Model for Ce(IV) consumption by metal components and regeneration by O 3 in a static mixer is developed and validated. • Reducing acidity of nitric acid limits the treatment batch time of components. • Valency of the salt doesn't affect the component corrosion in long run. • An ozonator of capacity 40–80 g/h is suitable for treating 10 kg steel components per batch in 65 L cerium solution. • The process is well-suited for the surface removal or decontamination of components of all geometries.

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Publication Details

Journal
Progress in Nuclear Energy
Published
2024-10-31
DOI
https://doi.org/10.1016/j.pnucene.2024.105492
Citations
2
Primary Topic
Hydrogen embrittlement and corrosion behaviors in metals
Type
article
Field-Weighted Citation Impact
0.34
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article

Mathematical modeling of ozone assisted cerium redox process for the surface removal of stainless steel components using a static mixer as gas-liquid contactor

Dayamoy Banerjee, Shaji Karunakaran, Vishakha Patel, Nirvik Sen et al.
2 citations
Progress in Nuclear Energy
Hydrogen embrittlement and corrosion behaviors in metals
0.34
article

Mathematical modeling of ozone assisted cerium redox process for the surface removal of stainless steel components using a static mixer as gas-liquid contactor

Dayamoy Banerjee, Shaji Karunakaran, Vishakha Patel, Nirvik Sen, Sukhdeep Singh, Sanjay Kumar
article en
2 citations

Abstract

This paper deals with a cerium based redox chemical process which is used for the surface removal and decontamination of stainless steel components arising from the operation and decommissioning of nuclear facilities. The process involves the corrosion of top contaminated metal surface (∼10–50 μm) by highly oxidizing Ce(IV) ions, in order to remove the entrapped radionuclides . The reduced Ce(III) ions thus generated after the oxidation of metal surface are continuously oxidized back to Ce(IV) by ozone. In this work, a lumped parameter model, accounting for the reduction of Ce(IV) to Ce(III) by steel components and the simultaneous oxidation of Ce(III) to Ce(IV) by ozone in a static mixer , has been developed. The model is experimentally validated by carrying out a corrosion experiment at 5 L scale in ∼0.4 M solution of Ce(IV) in 4 M HNO 3 at room temperature, by using non-radioactive AISI SS304L stainless steel components of different geometries viz. plate, pipe, elbow and T-Joint with a total surface area of 348 cm 2 . Using the validated model, design simulations of a pilot metal decontamination facility are carried out, to illustrate the effect of process parameters on the equilibrium Ce(IV) concentration in the loop, which is critical to component corrosion and decontamination. Simulation results show that, for a given initial cerium salt concentration , increasing the gas/liquid flow rate, ozone concentration, initial nitric acid concentration, and solution volume reduces the rate of fall of equilibrium Ce(IV) concentration with time. However, an increase in the temperature and surface area of the components enhances the rate of fall of equilibrium concentration of Ce(IV) with time. Additionally, reducing acidity of nitric acid has been found to limit the treatment time of components. Furthermore, the choice of a Ce(III) or Ce(IV) salt, as a source of cerium ions, has been shown to have no effect on the corrosion of metal components in a long run, when ozone regeneration of Ce(IV) is employed. Among the components of various geometries, relatively higher corrosion rates have been observed for the components with a curved geometry or a weld joint . SEM images of the welded and non-welded components show the occurrence of intergranular corrosion due to ozonated Ce(IV) solution, which is the likely mechanism for the removal of radionuclides from the metal surface. (Image Resolution: 1197 × 900 pixels). • Model for Ce(IV) consumption by metal components and regeneration by O 3 in a static mixer is developed and validated. • Reducing acidity of nitric acid limits the treatment batch time of components. • Valency of the salt doesn't affect the component corrosion in long run. • An ozonator of capacity 40–80 g/h is suitable for treating 10 kg steel components per batch in 65 L cerium solution. • The process is well-suited for the surface removal or decontamination of components of all geometries.

Progress in Nuclear EnergyVol. 178
Openalex Percentile: Top 51%
Hydrogen embrittlement and corrosion behaviors in metals
0.34
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