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On the chemical compatibility between Zr-4 substrate and well-bonded Cr_2AlC coating 被引量:3

On the chemical compatibility between Zr-4 substrate and well-bonded Cr_2AlC coating
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摘要 Accident tolerant fuel(ATF) for the light water reactor has gained wide attentions after the Fukushima accident. To enhance the accident-tolerance of the nuclear system, one strategy is to modify the Zr-based alloy cladding surface with advanced ceramic coating. In this work, monolithic and dense Cr_2AlC coating has been synthesized by magnetron sputtering. The as-grown Cr_2AlC coating exhibits good chemical compatibility with Zr-based alloy substrate as well as mechanical integrity under both pull-off and scratch tests. The coating system also presents moderate thermochemical compatibility at 800℃ but degrades above 1000℃ under simulated loss-of-coolant accident(LOCA) conditions. Accident tolerant fuel(ATF) for the light water reactor has gained wide attentions after the Fukushima accident. To enhance the accident-tolerance of the nuclear system, one strategy is to modify the Zr-based alloy cladding surface with advanced ceramic coating. In this work, monolithic and dense Cr_2AlC coating has been synthesized by magnetron sputtering. The as-grown Cr_2AlC coating exhibits good chemical compatibility with Zr-based alloy substrate as well as mechanical integrity under both pull-off and scratch tests. The coating system also presents moderate thermochemical compatibility at 800 ℃ but degrades above 1000℃ under simulated loss-of-coolant accident(LOCA) conditions.
出处 《Journal of Materials Science & Technology》 SCIE EI CAS CSCD 2019年第1期1-5,共5页 材料科学技术(英文版)
基金 supported by the National Natural Science Foundation of China under Grant Nos. 51402311 and 51772302 the National Key R&D Program of China under Grant No. 2017YFB0703201
关键词 ACCIDENT TOLERANT fuel Cr2AlC COATING THERMOCHEMICAL compatibility Accident tolerant fuel Cr_2AlC coating Thermochemical compatibility
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