钢包层耐事故燃料对VVER-1200堆芯持续传热的影响

MD Tanzib Ehsan Sanglap, Sazidur Rahman Shahriar
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引用次数: 0

摘要

自从福岛第一核电站发生事故以来,人们对开发事故耐受燃料(ATF)以避免轻水反应堆发生事故的兴趣日益浓厚,因为硅化铀基燃料具有将氢危害降至最低的优异性能。同样,钢包层也是当今研究人员关注的焦点。本研究考察了硅化铀(即U3Si、U3Si2和U3Si5)与不同类型奥氏体钢(即AISI)结合使用以提高安全性能的可行性。采用三维(3D)计算流体力学(CFD)编码星形ccm+模型,对VVER-1200超临界水冷堆六角形燃料组件的传热性能进行了评估。利用星ccm+计算环境,利用可实现的K-Epsilon双层壁面湍流模型对部分燃料高度进行了试验分析。分析表明,U3Si2燃料与AISI-348包壳组合使用在VVER-1200反应堆堆芯中具有较低的中心燃料温值和良好的机械和热优势,优于其他ATF-AISI燃料包壳组件。本工作还推导出了一个经验传热系数方程,以指导今后对堆芯热分析的相关研究。
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Influence of Accident-Tolerant Fuel With Steel Cladding for Sustainable Heat Transfer in the Reactor Core of VVER-1200
Since the events at the Fukushima–Daiichi nuclear power plant, there has been increased interest in developing accident tolerant fuel (ATF) to avoid accidents for light water reactors where Uranium-Silicide-based fuel has an excellent field to minimize the hydrogen hazards. Similarly, steel cladding is at the center of attraction for researchers nowadays. In this research, the feasibility of using Uranium-Silicides (i.e., U3Si, U3Si2, and U3Si5) combined with different types of austenitic steel (i.e., AISI) was investigated to improve the safety performance. A three-dimensional (3D) computational fluid dynamics (CFD)-coded star ccm+ model was used to assess heat transfer performance in the hexagonal fuel assembly of a supercritical water-cooled reactor VVER-1200. Utilizing the computational environment of star ccm+, the test analysis was conducted for a portion of fuel height using the realizable K-Epsilon Two-Layer Wall turbulence model. This analysis showed that the combination of U3Si2 fuel with AISI-348 cladding got superiority over other ATF-AISI fuel-claddings assemblies to use in the reactor core of VVER-1200 because of their lower central fuel temperature value with good mechanical and thermal advantages. This work also derived an empirical heat transfer coefficient equation to guide the relevant future investigations on the thermal analysis of the core.
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