Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance
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1-s2.0-S1738573317307283-main.pdf
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Author(s)
Champagne, Victor
Sevecek, Martin
Gurgen, Anil
Seshadri, Arunkumar
Che, Yifeng
Wagih, Malik M.
Phillips, Bren Andrew
Shirvan, Koroush
Date Issued
January 2018
Journal
Nuclear Engineering and Technology
Publisher
Elsevier
Citation
Ševeček, Martin et al. “Development of Cr Cold Spray–coated Fuel Cladding with Enhanced Accident Tolerance.” Nuclear Engineering and Technology 50, 2 (March 2018): 229–236 © 2018 Elsevier
Version
Final published version
Abstract
Accident-tolerant fuels (ATFs) are currently of high interest to researchers in the nuclear industry and in governmental and international organizations. One widely studied accident-tolerant fuel concept is multilayer cladding (also known as coated cladding). This concept is based on a traditional Zr-based alloy (Zircaloy-4, M5, E110, ZIRLO etc.) serving as a substrate. Different protective materials are applied to the substrate surface by various techniques, thus enhancing the accident tolerance of the fuel. This study focuses on the results of testing of Zircaloy-4 coated with pure chromium metal using the cold spray (CS) technique. In comparison with other deposition methods, e.g., Physical vapor deposition (PVD), laser coating, or Chemical vapor deposition techniques (CVD), the CS technique is more cost efficient due to lower energy consumption and high deposition rates, making it more suitable for industry-scale production. The Cr-coated samples were tested at different conditions (500°C steam, 1200°C steam, and Pressurized water reactor (PWR) pressurization test) and were precharacterized and postcharacterized by various techniques, such as scanning electron microscopy, Energy-dispersive X-ray spectroscopy (EDX), or nanoindentation; results are discussed. Results of the steady-state fuel performance simulations using the Bison code predicted the concept's feasibility. It is concluded that CS Cr coating has high potential benefits but requires further optimization and out-of-pile and in-pile testing.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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Creative Commons Attribution-NonCommercial-NoDerivs License
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DOI of Published Version
https://doi.org/10.1016/J.NET.2017.12.011
