Pressure Drop Analysis of a Re-entrant Fuel Channel in a Pressure-Channel Type Super Critical Water-Cooled Reactor

被引:0
|
作者
Maghsoudi, S. [1 ]
Peiman, W. [1 ]
Pioro, I. [1 ]
Gabriel, K. [2 ]
机构
[1] Univ Ontario, Inst Technol, Fac Energy Syst & Nucl Sci, Oshawa, ON, Canada
[2] Univ Ontario, Inst Technol, Fac Engn & Appl Sci, Oshawa, ON, Canada
关键词
SCWR; Pressure Drop; Nuclear Reactor; Generation IV;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Pressure drop calculation and temperature profiles associated with fuel and sheath are important aspects of a nuclear reactor design. The main objective of this paper is to determine the pressure drop in a fuel channel of a SuperCritical Water-cooled Reactor (SCWR). One-dimensional steady-state thermal-hydraulic analysis was conducted. In this study, the pressure drops due to friction, acceleration, local losses, and gravity were calculated at supercritical conditions. The total pressure drop due to all these parameters was between 108 and 121 kPa.
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页数:9
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