Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation

The influence has been studied of thermo-mechanical treatment, sensitization conditions, and neutron irradiation on the pitting corrosion resistance of austenitic 316LN stainless steel variants in 10% FeCl[subscript 3]·6H[subscript 2]O at 22 °C. Variants of this steel were modified with additions of...

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Main Authors: Merezhko, D. A., Merezhko, M. S., Gussev, M. N., Busby, J. T., Maksimkin, O. P., Garner, F. A., Short, Michael P
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Language:en_US
Published: Springer International Publishing 2018
Online Access:http://hdl.handle.net/1721.1/118600
https://orcid.org/0000-0002-9216-2482
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author Merezhko, D. A.
Merezhko, M. S.
Gussev, M. N.
Busby, J. T.
Maksimkin, O. P.
Garner, F. A.
Short, Michael P
author2 Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
author_facet Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Merezhko, D. A.
Merezhko, M. S.
Gussev, M. N.
Busby, J. T.
Maksimkin, O. P.
Garner, F. A.
Short, Michael P
author_sort Merezhko, D. A.
collection MIT
description The influence has been studied of thermo-mechanical treatment, sensitization conditions, and neutron irradiation on the pitting corrosion resistance of austenitic 316LN stainless steel variants in 10% FeCl[subscript 3]·6H[subscript 2]O at 22 °C. Variants of this steel were modified with additions of nitrogen, manganese, copper, and tungsten, as well as testing cast, cold-rolled, grain boundary engineered (GBE), and as-received variants. It was found that the 316LN steel variant with additions of 0.2% N and 2% Mn had the best pitting corrosion resistance of all studied conditions. When irradiated in a light water reactor (LWR) to a maximum fluence of 3 × 1017 n/cm[superscript 2] (E > 1.1 meV, Tirr < 50 °C), neutron irradiation surprisingly increased the resistance of GBE steels to pitting corrosion. An anisotropy of corrosion resistance of GBE and cold rolled steels was observed. Keywords: Austenitic stainless steel, Alloying, Nitrogen, Tungsten, Copper, Sensitization, Pitting corrosion, Grain boundary engineering
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spelling mit-1721.1/1186002022-09-23T14:14:31Z Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation Merezhko, D. A. Merezhko, M. S. Gussev, M. N. Busby, J. T. Maksimkin, O. P. Garner, F. A. Short, Michael P Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Short, Michael Philip Short, Michael P The influence has been studied of thermo-mechanical treatment, sensitization conditions, and neutron irradiation on the pitting corrosion resistance of austenitic 316LN stainless steel variants in 10% FeCl[subscript 3]·6H[subscript 2]O at 22 °C. Variants of this steel were modified with additions of nitrogen, manganese, copper, and tungsten, as well as testing cast, cold-rolled, grain boundary engineered (GBE), and as-received variants. It was found that the 316LN steel variant with additions of 0.2% N and 2% Mn had the best pitting corrosion resistance of all studied conditions. When irradiated in a light water reactor (LWR) to a maximum fluence of 3 × 1017 n/cm[superscript 2] (E > 1.1 meV, Tirr < 50 °C), neutron irradiation surprisingly increased the resistance of GBE steels to pitting corrosion. An anisotropy of corrosion resistance of GBE and cold rolled steels was observed. Keywords: Austenitic stainless steel, Alloying, Nitrogen, Tungsten, Copper, Sensitization, Pitting corrosion, Grain boundary engineering 2018-10-18T13:53:59Z 2018-10-18T13:53:59Z 2017-10 2017-08 Article http://purl.org/eprint/type/ConferencePaper 978-3-319-67243-4 978-3-319-67244-1 2367-1181 2367-1696 http://hdl.handle.net/1721.1/118600 Merezhko, D. A., et al. “Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation.” Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, 13-17 August, 2017, Portland, Oregaon, edited by John H Jackson et al., Springer International Publishing, 2018, pp. 1125–40. https://orcid.org/0000-0002-9216-2482 en_US http://dx.doi.org/10.1007/978-3-319-67244-1_71 Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors Creative Commons Attribution-Noncommercial-Share Alike http://creativecommons.org/licenses/by-nc-sa/4.0/ application/pdf Springer International Publishing Prof. Short
spellingShingle Merezhko, D. A.
Merezhko, M. S.
Gussev, M. N.
Busby, J. T.
Maksimkin, O. P.
Garner, F. A.
Short, Michael P
Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title_full Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title_fullStr Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title_full_unstemmed Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title_short Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation
title_sort investigation of pitting corrosion in sensitized modified high nitrogen 316ln steel after neutron irradiation
url http://hdl.handle.net/1721.1/118600
https://orcid.org/0000-0002-9216-2482
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