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Yang Xu, Liu-Tao Chen, Changyuan Gao, Jun Tan et autres
Abstract Zirconium alloys are one of the main cladding materials in pressurized water reactors. Corrosion resistance of zirconium alloy cladding weld is one of the most important factor affecting fuel integrity. CZ zirconium alloys have been recently developed for advanced PWR fuel …
cn (code pays fourni par la source)
Minli Chen, Changyuan Gao, Guoliang Zhang, Lin Shi et autres
Abstract CZ Alloys, including CZ1 and CZ2, are new advanced zirconium alloys developed by China General Nuclear Power Group. This paper presents the oxidation behaviour of CZ Alloys and Zircaloy-4 in flowing steam. A SETSYS Evolution TGA (ThermoGravimetric Analyzer) is used for …
cn (code pays fourni par la source)
Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun et autres
Abstract This paper is dealing with the iodine-induced stress corrosion cracking behavior of CZ2 zirconium alloy which is developed by China General Nuclear Power Group. The alloy in this study was fabricated with four different final annealing temperature in the range of …
cn (code pays fourni par la source)
Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu et autres
Abstract Based on the composition of CZ1 alloy and CZ2 alloy, guide tubes were fabricated. The performance of CZ1 and CZ2 alloy guide tube was studied. Through microscopic observation, it can be seen that the CZ alloy guide tube has a completely …
cn (code pays fourni par la source)
Q.Y. Lv, Libin Zhang, Minli Chen, Changyuan Gao et autres
Abstract This paper conducts in-depth research on zirconium alloys by combining results of out-of-pile corrosion and creep performance with microstructual and micro-chemical analysis using state-of-the-art (S)TEM, EDX and EBSD. The mechanism of different heat treatment processes on the macroscopic properties of zirconium …
cn (code pays fourni par la source)
Hansen Chen, Changyuan Gao, Liutao Chen, Xu Wang et autres
Abstract The corrosion behavior of zirconium alloys is closely related to the water chemistry and operating temperature of the primary circuit. The increase of operating temperature, Li concentration and pH value will have a significant negative impact on the corrosion behavior of …
cn (code pays fourni par la source)
Jieming Huang, Changyuan Gao, Liutao Chen, Xu Wang et autres
Abstract CZ2 alloy is a new Zr-Nb zirconium alloy independently developed by China Nuclear Power Research and Technology Institute (CNPRI), which has independent intellectual property rights. Zirconium will react with coolant to absorb hydrogen in reactor service, which will degrade the performance …
cn (code pays fourni par la source)
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