| Original Papers |
| Research Papers |
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Visualization experimental research on the movement characteristics of bubbles escaping from twin-orifice wall
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by HUANG Ying, GAO Puzhen, WANG Chaoqun, WANG Zhongyi
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106 |
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Modeling of natural circulation system with and without reactivity feedback
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by CHEN Xianbing, and GAO Puzhen
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114 |
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Requirements and experiences on a sustainable digital twin platform for dependable studies of thermal processes dynamics
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by JOKELAINEN Miikka, PORKHOLM Kari, and JUSLIN Kaj
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122 |
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Regression model for crack severity estimation in NPP
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by AYODEJI Abiodun, and LIU Yong-kuo
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132 |
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Effect analysis of ship motions on marine small modular reactor under full power operation condition
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by CHENG Kun, MENG Tao, LIU Zheng, and TAN Sichao
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140 |
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A voxelization modeling algorithm for point-kernel simulations on 3dsMax files
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by YANG Li-qun, LIU Yong-kuo, and LI Meng-kun
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148 |
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A point cloud based method for radiation source representation for cutting operation in the decommissioning of nuclear facilities
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by CHAO Nan, LIU Yong-kuo, XIA Hong, and YANG Li-qun
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154 |
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Distance information display system for supporting decom-missioning work of nuclear power plants
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by MIKI Naoya, HARAZONO Yuki, ISHII Hirotake, SHIMODA Hiroshi, and KOUDA Yuya
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162 |
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Simulation of pressurizer water level and causes of false water level in marine conditions
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by YANG Bo, XIA Hong, and ZHANG Ji-yu
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172 |
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Safety analysis on steam line break accident of integral PWR
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by SUN Lin, PENG Minjun, and XIA Genglei
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181 |
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Study of blind source separation algorithm based on particle swarm optimization in nuclear power background
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by MA Xintong, XIA Hong, and ZHU Shaomin
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187 |
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Comparative study on core designs of an annular, prismatic HTGR for passive decay heat removal
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by SAMBUU Odmaa, TERBISH Jamiyansuren, BYAMBAJAV Munkhbat, and NANZAD Norov
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194 |
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Preliminary neutronic analyses on VHTR core design
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by SAMBUU Odmaa, BATSAIKHAN Khukhsuvd, TERBISH Jamiyansuren, BYAMBAJAV Munkhbat, and NANZAD Norov
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200 |
| |
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The comparison between the direct and second side passive residual heat removal system, and system optimized
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by LYU Xing, PENG Minjun, and XIA Genglei
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206 |
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Visualization study on premature CHF during two phase flow instability in narrow, vertical, rectangular channel
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by HE Haisha, CAO Xiaxin, HU Jian, LI Na, and YANG Peixun
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212 |
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Numerical optimization on the geometrical factors of a subsonic air-air ejector
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by HU Jian, CAO Xiaxin, HE Haisha, MENG Zhaoming, and DING Ming
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221 |
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A computer code for the thermal-hydraulic analysis of a helical-coil-type once through steam generator
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by DING Xueyou, WEN Qinglong, WANG Hongyang, RUAN Shenhui, and CHEN Zhiqiang
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229 |
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| Research Reviews |
| |
Issues associated with DWO in recent studies
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by BELLO Mary-Olubunmi, PENG Minjun, and XIA Genglei
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238 |
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Study on using the Monte Carlo simulation code for characterization of nuclear materials
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by K. ABD EL Gawad, ZHANG Zhijian, and YUSHOU Song
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243 |
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Intelligent fault diagnosis for nuclear power plant based on deep belief network and support vector machine
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by ZHOU Wen, LIU Yong-kuo, XIA Hong, and LIU Peng-fei
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252 |
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| Technical Reports |
| |
Application of blind source separation to fault diagnosis of nuclear power equipment
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by JIANG Yingying, XIA Hong, and ZHU Shaomin
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257 |
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