[1] | Fu Junsen, Xiao Yao, Chen Shuo, Zhang Wei, Cong Tenglong, Gu Hanyang. Experiment Study on Critical Heat Flux of 19-Pin Helical Cruciform Fuel Assembly[J]. Nuclear Power Engineering, 2024, 45(3): 132-138. doi: 10.13832/j.jnpe.2024.03.0132 |
[2] | Liu Wei, Guo Junliang, Zhang Dan, Gui Miao, Hu Ying, Liu Yang. Experimental Study on Critical Heat Flux of Vertical Square Channel with Single Rod[J]. Nuclear Power Engineering, 2022, 43(1): 42-47. doi: 10.13832/j.jnpe.2022.01.0042 |
[3] | Liu Wei, Peng Shinian, Jiang Guangming, Liu Yu, Deng Jian, Hu Ying, Liu Xiaobo. Review on Development of Critical Heat Flux Mechanistic Model[J]. Nuclear Power Engineering, 2021, 42(3): 211-218. doi: 10.13832/j.jnpe.2021.03.0211 |
[4] | Jiang Botao, Huang Xinbo. Prediction of Critical Heat Flux Based on Gaussian Process Regression[J]. Nuclear Power Engineering, 2019, 40(5): 46-50. |
[5] | Li Haoxiang, Peng Chuanxin, Zan Yuanfeng. Experimental Investigation on Critical Heat Flux in Horizontal Tube[J]. Nuclear Power Engineering, 2018, 39(1): 43-46. doi: 10.13832/j.jnpe.2018.01.0043 |
[6] | Peng Chuanxin, Chen Bingde, ZhuO Wenbin, Zan Yuanfeng, Liu Liang, Huang Yanping, Xu Jianjun. Phenomenon and Analysis of Natural Circulation CHF[J]. Nuclear Power Engineering, 2017, 38(3): 7-11. doi: 10.13832/j.jnpe.2017.03.0007 |
[7] | Qin Shengjie, Lang Xuemei, Xie Shijie, Li Pengzhou, Zhang Junyi, Liu Wenxing, Zhuo Wenbin. Benchmark Experiment on Critical Heat Flux of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2016, 37(5): 1-3. doi: 10.13832/j.jnpe.2016.05.0001 |
[8] | Guo Rui, Liu Xiaojing, Cheng Xu, Yu Hongxing. Theoretical Investigation on Critical Heat Flux at Inclined Heater Surface in Low Pressure[J]. Nuclear Power Engineering, 2016, 37(4): 11-14. doi: 10.13832/j.jnpe.2016.04.0011 |
[9] | Zhao Dawei, Liu Wenxing, Xiong Wanyu, Zan Yuanfeng, Yang Zumao. Theoretical Research on DNB-type Critical Heat Flux with Non-Uniform Axial Heat Flux Distribution[J]. Nuclear Power Engineering, 2016, 37(1): 18-22. doi: 10.13832/j.jnpe.2016.01.0018 |
[10] | Liu Ye, Zhao Dawei, Liu Wenxing, Zan Yuanfeng. Theoretical Study on Critical Heat Flux in Vertical Narrow Tube with Axial Power Step[J]. Nuclear Power Engineering, 2016, 37(4): 6-10. doi: 10.13832/j.jnpe.2016.04.0006 |
[11] | Liu Wenxing, Peng Jingfeng, Xu Jianjun, Huang Yanping, Yang Zumao. Theoretical Study on Effect of Flow Channel Local Inclination on Critical Heat Flux[J]. Nuclear Power Engineering, 2015, 36(4): 8-11. doi: 10.13832/j.jnpe.2015.04.0008 |
[12] | Zhang Zhen, Xiao Zejun, Yan Xiao, Qin Shengjie, Huang Yanping, Chen Bingde. Study on Effect of Rolling on Two-Phase Frictional Pressure Drop in Narrow Channels[J]. Nuclear Power Engineering, 2014, 35(1): 56-59. |
[13] | Sheng Cheng, Zhou Tao, JU Zhongyun, Huang Yanping, Xiao Zejun. Experimental Evaluation of Critical Heat Flux Calculation Models of Rectangular Channel[J]. Nuclear Power Engineering, 2014, 35(1): 52-55. |
[14] | PAN Jie, YANG Dong, XIAO Rong-ge, DENG Zhian. Critical Heat Flux Prediction Model for Low Quality Flow Boiling[J]. Nuclear Power Engineering, 2013, 34(4): 58-63. |
[15] | HONG Gang, YAN Xiao, LI Yan, XIAO Ze-jun, HUANG Yan-ping. Distribution of Sliding Bubble Diameter along Axial Direction in Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2012, 33(S1): 10-13. |
[16] | LI Yong, XIONG Wanyu, YAN Xiao, HUANG Yanping. Experimental Investigation of Critical Heat Flux in Rectangular Channels with Different Gap Sizes[J]. Nuclear Power Engineering, 2012, 33(3): 42-45. |
[17] | XIE Shijie, XIONG Wanyu, WANG Jun. Critical Heat Flux Tests in Rectangular Channel with Asymmetrical Heat Flux[J]. Nuclear Power Engineering, 2012, 33(1): 34-38. |
[18] | XU Jianjun, CHEN Bingde, WANG Xiaojun. Analysis and Discussion of Flow Boundary Layer in Fully Turbulent of Narrow Rectangular Channel[J]. Nuclear Power Engineering, 2011, 32(1): 95-98,103. |
[19] | WEN Qing-long, CHEN Jun, ZHAO Hua. Experimental Study on Pool Boiling Critical Heat Flux in Inclined Confined Spaces[J]. Nuclear Power Engineering, 2011, 32(6): 34-37. |
[20] | ZHOU Lei, LIU Xiangfeng, YAN Xiao, HUANG Yanping, CHEN Bingde. Numerical Prediction of Critical Heat Flux in Narrow Rectangular Channels[J]. Nuclear Power Engineering, 2011, 32(4): 46-51. |