본문 바로가기
KERD
논문KCI 등재

An experimental study of the CHF in a square channel with non-uniformly heated rod under low pressure and low flow conditions

2

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

Experimental research on critical heat flux (CHF) was carried out in a vertical square channel with non-uniformly heated rod at low pressure and low flow conditions. The influence of inlet subcooling on CHF was also investigated. The results showed that the CHF position of the non-uniformly heat flux distribution mainly appeared in the middle and lower part of the heater rod. More significantly, it was found that CHF was enhanced with the rise of the inlet subcooling. The CHF data measured in this experiment were also assessed with the commonly used CHF empirical correlations suitable for low pressure and low flow. The results indicated that the general correlations predicting for CHF of uniform heat flux distribution were not applicable for prediction CHF of nonuniform heat flux distribution and these correlations usually overestimated the experimental values. In addition, The F-factor approach proposed by Tong was used to predict the experimental data and the error predicted by F-factor were mostly between 30 % and 50 %. Finally, F-factor was modified based on experimental data and the error between the predicted value and experimental results was between 0 and 30 %, and most of the data was between 0 and 20 %.

Abstract

Experimental research on critical heat flux (CHF) was carried out in a vertical square channel with non-uniformly heated rod at low pressure and low flow conditions. The influence of inlet subcooling on CHF was also investigated. The results showed that the CHF position of the non-uniformly heat flux distribution mainly appeared in the middle and lower part of the heater rod. More significantly, it was found that CHF was enhanced with the rise of the inlet subcooling. The CHF data measured in this experiment were also assessed with the commonly used CHF empirical correlations suitable for low pressure and low flow. The results indicated that the general correlations predicting for CHF of uniform heat flux distribution were not applicable for prediction CHF of nonuniform heat flux distribution and these correlations usually overestimated the experimental values. In addition, The F-factor approach proposed by Tong was used to predict the experimental data and the error predicted by F-factor were mostly between 30 % and 50 %. Finally, F-factor was modified based on experimental data and the error between the predicted value and experimental results was between 0 and 30 %, and most of the data was between 0 and 20 %.

관련 논문AI추천

Experimental Investigation on Critical Heat Flux in Bilaterally Heated Annulus with equal heat flux on both sidesGui Miao, Guo Junliang, Kong Huanjun, Peng Yujiao, Shan Jianqiang, Wu Pan한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제9호A Method for Critical Heat Flux Prediction in Vertical Round Tubes with Axially Non-uniform Heat Flux Profile심재우한국해양공학회 · 한국해양공학회지2008 · 제22권 제1호Numerical investigation of the critical heat fl ux in a 5 × 5 rod bundle with multi-gridLixin Yang, Qian Peng, Shihao Yang, Wei Liu, Xi Chen, Yu Liu, Zemin Shang, Zihao Tian한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제5호Experimental study on the Influence of Heating Surface Inclination Angle on Heat Transfer and CHF performance for Pool BoilingChenglong Wang, Dalin Zhang, G.H. Su, Jian Deng, Panxiao Li, Suizheng Qiu, Wenxi Tian한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제1호Water film covering characteristic on horizontal fuel rod under impinging cooling conditionChen Ronghua, Qiu Suizheng, Su G.H., Tian Wenxi, Wang Bowei, Zhang Penghui한국원자력학회 · Nuclear Engineering and Technology2022 · 제54권 제11호Numerical study on the size effect on the mixing in 2×1, 3×3 and 5×5 rod bundle subchannelsHan Bin, Liu Aiguo, Liu Shenghui, Yang Bao-Wen, Yin Yuanyuan, zhu Xiaoliang한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제12호

이 간행물의 다른 논문 (49건)