Zirconium alloys remain as the main cladding materials in most water reactors. CZ zirconium alloy is recently developed for advanced PWR fuel assembly (STEP) designed by China General Nuclear Power Group (CGN). There are two kinds of zirconium alloys, designated as CZ1 and CZ2 respectively. It is well known that creep property is one of the most important characteristics to evaluate the integrated performance of new commercial alloys. In this study, we have collected the creep date of CZ alloys heat-treated at different temperatures. The result shows that the creep rates of the zirconium alloys enlarge with the creep stress in the temperature of 375 °C. The creep resistance is improved with the increasing annealing temperature. The creep resistance of CZ-RXA (high temperature) is better than CZ-SRA (low temperature). The creep rate of CZ alloys at relatively lower annealing temperature is much larger than that at higher annealing temperature. At the given stress condition, the creep behaviors of different annealed CZ alloys are found to have almost the same tendency. In addition, the creep rate of CZ1 is smaller than CZ2 at the same annealing temperature.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5781-6
PROCEEDINGS PAPER
Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings
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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Liu-tao Chen,
Liu-tao Chen
China Nuclear Power Technology Research Institute, Shenzhen, China
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Dun-gu Wen,
Dun-gu Wen
China Nuclear Power Technology Research Institute, Shenzhen, China
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Hong Zou,
Hong Zou
China Nuclear Power Technology Research Institute, Shenzhen, China
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Chang-yuan Gao,
Chang-yuan Gao
China Nuclear Power Technology Research Institute, Shenzhen, China
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Xu Wang,
Xu Wang
China Nuclear Power Technology Research Institute, Shenzhen, China
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Si-si Dong,
Si-si Dong
China Nuclear Power Technology Research Institute, Shenzhen, China
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Wei-jun Wang
Wei-jun Wang
China Institute of Atomic Energy, Beijing, China
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Yang Xu
China Nuclear Power Technology Research Institute, Shenzhen, China
Jun Tan
China Nuclear Power Technology Research Institute, Shenzhen, China
Liu-tao Chen
China Nuclear Power Technology Research Institute, Shenzhen, China
Dun-gu Wen
China Nuclear Power Technology Research Institute, Shenzhen, China
Hong Zou
China Nuclear Power Technology Research Institute, Shenzhen, China
Chang-yuan Gao
China Nuclear Power Technology Research Institute, Shenzhen, China
Xu Wang
China Nuclear Power Technology Research Institute, Shenzhen, China
Si-si Dong
China Nuclear Power Technology Research Institute, Shenzhen, China
Wei-jun Wang
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE25-67054, V003T02A039; 5 pages
Published Online:
October 17, 2017
Citation
Xu, Y, Tan, J, Chen, L, Wen, D, Zou, H, Gao, C, Wang, X, Dong, S, & Wang, W. "Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application. Shanghai, China. July 2–6, 2017. V003T02A039. ASME. https://doi.org/10.1115/ICONE25-67054
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