Reaction Capsule Design for Interaction of Heavy Liquid Metal Coolant, Fuel Cladding, and Simulated JOG Phase at Accident Conditions

Author:

Tarı Doğaç1ORCID,Retegan Vollmer Teodora1ORCID,Geers Christine2ORCID

Affiliation:

1. Nuclear Chemistry and Industrial Materials Recycling, Department of Chemistry and Chemical Engineering, Chalmers University of Technology, 412 96 Gothenburg, Sweden

2. Environmental Inorganic Chemistry, Department of Chemistry and Chemical Engineering, Chalmers University of Technology, 412 96 Gothenburg, Sweden

Abstract

High temperature corrosion of fuel cladding material (15-15Ti) in high burn-up situations has been an important topic for molten metal-cooled Gen-IV reactors. The present study aims to investigate the simultaneous impact of liquid lead (coolant side) and cesium molybdate (fuel side) on the cladding tube material. A capsule was designed and built for experiments between 600 °C and 1000 °C. In order to simulate a cladding breach scenario, a notch design on the cladding tube was investigated pre- and postexposure. Material thinning by corrosion and leaching at temperatures ≥ 900 °C caused breaches at the notches after 168 h exposure. The temperature dependent cladding thinning phenomenon was used for kinetic interpretation. As the first of a two-part study, this paper will focus on the exposure capsule performance, including metallographic cross-section preparation and preliminary results on the interface chemistry.

Funder

European Commission

Publisher

MDPI AG

Reference51 articles.

1. Generation IV International Forum: A decade of progress through international cooperation;Kelly;Prog. Nucl. Energy,2014

2. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities;Murty;J. Nucl. Mater.,2008

3. Fazio, C., Sobolev, V., Aerts, A., Gavrilov, S., Lambrinou, K., Schuurmans, P., Gessi, A., Agostini, P., Ciampichetti, A., and Martinelli, L. (2015). Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-Hydraulics and Technologies, Organisation for Economic Co-Operation and Development.

4. Dissolution and oxidation behaviour of various austenitic steels and Ni rich alloys in lead-bismuth eutectic at 520 °C;Roy;J. Nucl. Mater.,2016

5. Buckthorpe, D. (2017). Structural Materials for Generation IV Nuclear Reactors, Elsevier.

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