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锆合金包壳在模拟压水堆一回路冷却剂中的表面污垢沉积行为研究 被引量:3

Laboratory Simulation of Crud Deposition on Zr-alloy Fuel Cladding in Simulated Pressurized Water Reactor Primary Coolant
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摘要 阐述了影响燃料包壳表面污垢沉积行为的主要因素,通过设计并开展针对国产锆合金燃料包壳的污垢沉积试验,成功制备出含多孔基体和烟囱结构主要元素组成的燃料包壳氧化物污垢,污垢的主要成分为NiFe_(2)O_(4)、Fe_(2)O_(3)和NiO,并在污垢内部检测到LiBO_(2)的析出,实现了对PWR堆芯燃料包壳污垢沉积的实验室模拟。 For pressurized water reactor(PWR)nuclear power plant,crud on fuel cladding is derived from primary corrosion products,which deposit on the surface of fuel assembly.Crud deposition is affected by the coupling effects between the primary coolant environment and the thermal-hydraulic condition.The crud on cladding surface can affect the operation safety and economic benefits of the reactor.In this paper,the main factors affecting the crud deposition behavior on the surface of fuel cladding were described.The crud deposition process on the domestic Zr-alloy cladding was assessed via a home-made experimental set.As a result,the porous and chimney-like crud was successfully reproduced,while which composed mainly of NiFe_(2)O_(4),Fe_(2)O_(3) and NiO,besides the precipitation of LiBO_(2) was detected.The experiment results indicated that the crud deposition on PWR fuel cladding could be reliably reproduced through laboratory simulation.
作者 廖家鹏 毛玉龙 金德升 厉井钢 LIAO Jiapeng;MAO Yulong;JIN Desheng;LI Jinggang(China Nuclear Power Technology Research Institute,Shenzhen 518000,China)
出处 《中国腐蚀与防护学报》 CAS CSCD 北大核心 2023年第1期197-201,共5页 Journal of Chinese Society For Corrosion and Protection
基金 中国博士后科学基金(2021M703023)。
关键词 压水堆 锆合金包壳 污垢沉积 一回路冷却剂 pressurized water reactor zirconium alloy cladding crud deposition primary coolant
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