Breakaway oxidation is a potential fuel failure mechanism during a loss-of-coolant accident (LOCA), especially small-break LOCA. Two kinds of new advanced zirconium alloy, CZ1 and CZ2, were developed by China Nuclear Power Research and Technology Institute of China General Nuclear Power Group. The breakaway oxidation behavior of CZ1 and CZ2 was studied. The outer surface of all samples was examined visually and photographed. After 2730s oxidation in steam, the outer surface of CZ1 alloy sample and CZ2 alloy sample remained lustrous-black. The outer surface of CZ1 sample oxidized in steam at 1000 °C for 4181s was grey, but under the same experimental conditions the outer surface of CZ2 sample was still lustrous black. The hydrogen pickup content of different oxidation time was measured. The samples with grey appearance showed significant hydrogen pickup. The microstructure was observed by optical microscope. Evolution of oxide structure was described, and the mechanism was discussed.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5145-6
PROCEEDINGS PAPER
Investigation on Breakaway Oxidation Behavior of CZ Alloys
Chang-yuan Gao,
Chang-yuan Gao
China Nuclear Power Technology Research Institute, Shenzhen, China
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Liu-tao Chen,
Liu-tao Chen
China Nuclear Power Technology Research Institute, Shenzhen, China
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Lin Shi,
Lin Shi
China Nuclear Power Technology Research Institute, Shenzhen, China
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Yang Xu,
Yang Xu
China Nuclear Power Technology Research Institute, Shenzhen, China
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Jun Tan,
Jun Tan
China Nuclear Power Technology Research Institute, Shenzhen, China
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Yong-jun Deng
Yong-jun Deng
China Nuclear Power Technology Research Institute, Shenzhen, China
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Chang-yuan Gao
China Nuclear Power Technology Research Institute, Shenzhen, China
Liu-tao Chen
China Nuclear Power Technology Research Institute, Shenzhen, China
Lin Shi
China Nuclear Power Technology Research Institute, Shenzhen, China
Yang Xu
China Nuclear Power Technology Research Institute, Shenzhen, China
Jun Tan
China Nuclear Power Technology Research Institute, Shenzhen, China
Yong-jun Deng
China Nuclear Power Technology Research Institute, Shenzhen, China
Paper No:
ICONE26-81541, V003T02A026; 5 pages
Published Online:
October 24, 2018
Citation
Gao, C, Chen, L, Shi, L, Xu, Y, Tan, J, & Deng, Y. "Investigation on Breakaway Oxidation Behavior of CZ Alloys." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. London, England. July 22–26, 2018. V003T02A026. ASME. https://doi.org/10.1115/ICONE26-81541
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