An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR

被引:0
作者
Pathak, S. P. [1 ,2 ]
Velusamy, K. [1 ]
Devan, K. [2 ]
Kumar, V. A. Suresh [2 ]
机构
[1] Indira Gandhi Ctr Atom Res, Kalpakkam 603102, Tamil Nadu, India
[2] Indira Gandhi Ctr Atom Res, Reactor Design & Technol Grp, Kalpakkam 603102, Tamil Nadu, India
关键词
Steam generator; sodium-cooled fast reactor; two-phase pressure drop; experiments; two-phase frictional multiplier; FLOW;
D O I
10.1080/00295639.2023.2216127
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Due to the presence of sodium, it is a challenging task to achieve the reliable and safe operation of steam generators in a sodium-cooled fast reactor (SFR). Water flow oscillations in a two-phase flow system worsen the tube integrity. An accurate prediction of two-phase pressure drop is essential in designing steam generators to operate in a stable regime. Toward this, experiments have been carried out on an industrial-size 19-tube model sodium-heated steam generator of 5.5-MW capacity to understand two-phase pressure drop characteristics at various operating conditions. The measured data are used to estimate the two-phase frictional pressure drop. The concept of a two-phase friction multiplier has been used in the present study. A significant variation in the two-phase frictional multiplier is seen with steam quality, whereas the variation of the two-phase friction multiplier is insignificant at saturated steam condition. Based on the experiments, complemented by computational model, a correlation has been developed for the two-phase frictional multiplier as a function of steam quality for sodium-heated once-through straight-tube steam generators.
引用
收藏
页码:804 / 817
页数:14
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