The Behavior of Analogues for RIS-affected AGR Cladding under Conditions Relevant to Wet Interim Storage : 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019

Howett, E. and Boxall, C. and Hambley, D. (2020) The Behavior of Analogues for RIS-affected AGR Cladding under Conditions Relevant to Wet Interim Storage : 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019. In: 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, 2019-09-22 - 2019-09-26, The Westin Seattle.

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Abstract

Due to radiation induced segregation (RIS) that occurs during fuel use in-reactor, portions of spent fuel cladding are predicted to have enhanced corrosion susceptibility during wet interim storage. The National Nuclear Laboratory UK have produced thermally sensitized analogues (20/25/Nb SS and 304H SS) for RIS-affected cladding to allow study of this effect without radiological risk. Here, we present a study of the corrosion properties of these simulants in order to gain insight into the behavior of real cladding under conditions relevant to wet storage. First, the degree of sensitization of the RIS-affected cladding analogues was verified. In these tests significant susceptibility to localized corrosion was observed. The effect of such vulnerability was analyzed under alkali corrosion conditions. Under open circuit conditions, XPS data indicates that the protective layer formed on the surface of thermally aged SS consists predominately of Fe and Cr oxides/hydroxides, with Fe oxide/hydroxide being the more dominant of the two especially in the case of 304H SS. Despite increased vulnerability and the decrease in Cr oxide/hydroxide in the surface layer, both heat treated samples were found to protected under pond water conditions and it would be expected that real RIS-affected cladding would be similarly passive under the same conditions. Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference.All rights reserved.

Item Type:

Contribution to Conference (Paper)

Journal or Publication Title:

14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019

Additional Information:

Conference code: 157481 Export Date: 19 March 2020 Funding details: Lancaster University Funding text 1: This work is supported by the National Nuclear Laboratory, Lancaster University and the Lloyd’s Register Foundation (award no. G0025) via provision of a PhD studentship for EH and support for CB. the Lloyd’s Register Foundation (award number G0025) for their support. The Lloyds Register Foundation is an independent charity that supports the advancement of engineering-related education, and funds research and development that enhances safety of life at sea, on land and in the air. References: English, C., Murphy, S., Perks, J., Radiation-induced Segregation in Metals (1990) J. Chem. Soc. Faraday Trans., 86, pp. 1263-1271; Allen, T., Busby, J., Was, G., Kenik, E., On the mechanism of radiation-induced segregation in austenitic Fe-Cr-Ni alloys (1998) J. Nucl. Mater., 255, pp. 44-58; Was, G., Assessment of radiation-induced segregation mechanisms in austenitic and ferritic-martensitic alloys (2011) J. Nucl. Mater., 411, pp. 41-50; Bates, J., Powell, R., Gilbert, E., Reduction of irradiation-induced creep and swelling in AISI 316 by compositional modifications (1980) Effects of Radiation on Materials: Proceedings of the Tenth International Symposium, pp. 713-734. , ASTM International; Whillock, G.O.H., Hands, B., Majchrowski, T., Hambley, D.I., Investigation of thermally sensitised stainless steels as analogues for spent AGR fuel cladding to test a corrosion inhibitor for intergranular stress corrosion cracking (2018) J. Nucl. Mater., 498, pp. 187-198; Norris, D.I., Baker, C., Titchmarsh, J., A study of radiation-induced sensitisation in 20/25/Nb steel by compositional profile measurements (1987) Materials for Nuclear Reactor Core Applications: Proceedings of the International Conference, pp. 277-283. , British Nuclear Energy Society; Taylor, C., Sumerling, R., Rhodes, D., (1982) The Development of Sensitised Structures in CAGR Fuel Pin Cladding: A Brief Summary of Recent WNL Observations; Outokumpu, (2013) High Temperature Austenitic Stainless Steel - Technical Report; (2015) Stainless Steel Data Sheet 304H, , Aalco; (2011) Grade Data Sheet, 304, p. 304L. , Atlas Steels. 304H; Richardson, T.J.A., (2009) Shreir's Corrosion, , Elsevier; Standard Practices for Detecting Susceptibility to Intergranular Attack in Austenitic Stainless Steels- A262, , ASTM International; Amadou, T., Sidhom, H., Braham, C., Double loop electrochemical potentiokinetic reactivation test optimization in checking of duplex stainless steel intergranular corrosion susceptibility (2004) Metall. Mater. Trans. A, 35, pp. 3499-3513; (2005) Corrosion Tests and Standards: Application and Interpretation, , ASTM International; Yeh, J.J., Lindau, I., Atomic subshell photoionization cross sections and asymmetry parameters: 1 - Z -103 (1985) At. Data Nucl. Data Tables, 32, pp. 1-155; Yu, C., Nguyen, T.D., Zhang, J., Young, D., Sulfur effect on corrosion behavior of Fe-20Cr(Mn, Si) and Fe-20Ni-20Cr-(Mn, Si) in CO2-H2O at 650C (2016) J. Electrochem. Soc., 163, pp. C106-C115; Gheno, T., Monceau, D., Zhang, J., Young, D.J., Carburisation of ferritic FeCr alloys by low carbon activity gases (2011) Corros. Sci., 53, pp. 2767-2777; Krot, N., (1999) Development of AIkaIine Oxidative Dissolution Methods for Chromium(III) Compounds Present in Hanford Site Tank Sludges; Olsson, C.O., Landolt, D., Passive films on stainless steels-chemistry, structure and growth (2003) Electrochim. Acta, 48, pp. 1093-1104; Rashid, M.W.A., Gakim, M., Rosli, Z.M., Azam, M.A., Formation of Cr23C6 during the sensitization of AISI 304 stainless steel and its effect to pitting corrosion (2012) Int. J. Electrochem. Sci., 7, pp. 9465-9477; Beverskog, B., Puigdomenech, I., Revised pourbaix diagrams for chromium at 25-300C (1997) Corros. Sci., 39, pp. 43-57; Beverskog, B., Puigdomenech, I., Revised pourbaix diagrams for nickel at 25-300C (1997) Corros. Sci., 39, pp. 969-980

Subjects:

?? chromium compoundscladding (coating)corrosive effectsdigital storagefuelsinterlocking signalsiron oxideslight water reactorslocalized corrosionnuclear fuel reprocessingalkali corrosioncorrosion propertycorrosion susceptibilitydegree of sensitizationopen c ??

Departments:

Faculty of Science and Technology > Engineering

ID Code:

142566

Deposited By:

ep_importer_pure

Deposited On:

18 Jun 2021 15:55

Refereed?:

Yes

Published?:

Published

Last Modified:

16 Jul 2024 08:04

URI:

https://eprints.lancs.ac.uk/id/eprint/142566