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摘要:
This paper presents a comparative analysis of different parameters such as enthalpy, moderator temperature, moderator density, flow velocity, pressure, and fuel temperature profile at the fuel pin cell level of PWR. Moreover, in this paper pitches to fuel pin radius ratio are varied from 2.3 to 4. The methods and implementation strategy are such that the coupled neutronic and thermal-hydraulic analysis is executed in a fully one dimensional (1D) manner. The thermal hydraulic is based on moderator/coolant mass and enthalpy equation together with one group diffusion equation for fuel pin. Modelling of fuel pin cell and subchannel is executed in two steps. First, the governing equations are derived assuming that all the parameters appearing in the equations are temperature independent. Fuel pin centerline temperature and radially averaged temperature equations are derived from Fourier laws of thermal conductivity. Finally, diffusion coefficient, fission cross-section and absorbing cross-section are evaluated with respect to the fuel pin temperature. The outcome will be helpful for further neutronics and thermal analysis of PWR. Thermal hydraulics parameter varies the maximum 30 percentage from the lowermost value.
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篇名 Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)
来源期刊 核科学与技术国际期刊(英文) 学科 医学
关键词 FUEL PIN PITCH Sub-Channel NEUTRONICS and Thermal Hydraulics
年,卷(期) 2019,(2) 所属期刊栏目
研究方向 页码范围 74-83
页数 10页 分类号 R73
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研究主题发展历程
节点文献
FUEL
PIN
PITCH
Sub-Channel
NEUTRONICS
and
Thermal
Hydraulics
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期刊影响力
核科学与技术国际期刊(英文)
季刊
2161-6795
武汉市江夏区汤逊湖北路38号光谷总部空间
出版文献量(篇)
72
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0
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0
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