Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions

被引:3
|
作者
Yodo, Tadakatsu [1 ]
Odaira, Naoya [2 ]
Ito, Kei [2 ]
Ito, Daisuke [2 ]
Saito, Yasushi [2 ]
机构
[1] Kyoto Univ, Grad Sch Energy Sci, Sakyo Ku, Kyoto 6068501, Japan
[2] Kyoto Univ Osaka, Inst Integrated Radiat & Nucl Sci, Kyoto, Japan
关键词
Critical heat flux; mechanistic model-based correlation; CHF correlation; DNB; liquid sublayer dryout model; CHF look-up table; thermal hydraulic; safety analysis; PWR type reactor; ROD BUNDLES; PREDICTION; WATER; CHF;
D O I
10.1080/00223131.2022.2091054
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
In this study, a mechanistic model-based correlation for the critical heat flux is proposed to meet the practical requirements for the design and safety analysis of pressurized water reactors. The correlation is based on a liquid sublayer dryout model for a single tube, which includes physical parameters, such as sublayer thickness and vapor blanket velocity, expressed as an explicit nondimensional equation and modified using a look-up table for critical heat flux to ensure a wide applicable range of coolant conditions. The correlation predicts a critical heat flux for the subcooled region in the pressure range of 0.1-18 MPa, mass velocity range of 500-8000 kg/m(2)s, and a thermal equilibrium quality ranging from -0.5 to -0.05 with high accuracy of the departure from nucleate boiling ratio limit based on a 95% probability and a 95% confidence of 1.20.
引用
收藏
页码:197 / 214
页数:18
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