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Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor
NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25
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    • Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor

    • “In the field of nuclear power plant fuel rod research, experts have analyzed the chemical interaction layer between zirconium alloy cladding and fuel pellets, revealing their structure and formation mechanism, providing important references for fuel rod design and safe operation.”
    • NUCLEAR TECHNIQUES   Vol. 46, Issue 9, Article number: 090602(2023)

    • DOI：10.11889/j.0253-3219.2023.hjs.46.090602    

      CLC： TL99

    • Received：10 February 2023，

      Revised：04 April 2023，

      Published：15 September 2023

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  • WANG Huacai,YANG Dawei,CHENG Huanlin,et al.Chemical interaction layer between uranium oxide fuel pellet and zirconium alloy cladding in pressurized water reactor[J].NUCLEAR TECHNIQUES,2023,46(09):090602. DOI： 10.11889/j.0253-3219.2023.hjs.46.090602.

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