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PROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025

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Journal Papers 42
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Experiment Research and Data Benchmarking of YBS Critical Experiment Facility Lead Reactor Core
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deleteLi, Xingjian; Zhu, Qingfu; Zhou, Qi; Xia, Zhaodong; Ning, Tong; Zhang, Zhenyang; Du, Zihan
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Bayesian Uncertainty Quantification and Sensitivity Analysis on Hydrogen Behavior in Zircaloy Cladding
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deleteGan, Meiqing; Liu, Rong
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Preliminary Research on Comparison and Selection of Types of Fuels for Fast Reactor
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deleteXiaochun, A. Jia; Yun, B. Hu
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Preparation and Properties of Micro-arc Oxidation Layer on Zircouium Alloy Surface
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deleteWang, Zhibin; Wu, Jinguo; Li, Mingyang; Cai, Zhenfang; Liu, Wei; Liu, Siyuan
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Neutronic-Thermal Coupling Analyses of U-50Zr Helical Cruciform Fuel Concepts Based on OpenMC Code and MOOSE Framework
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deleteDong, Yiliang; Wen, Qinglong
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Investigation of Hydrogen Diffusion and Deposition Behavior of Spiral Fuel in Pressurized Water Reactors
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deleteChen Nan; Ding Yuzhe; Xiang Fengrui; He Yanan; Zhang Jing; Wu Yingwei; Tian Wenxi; Su Guanghui; Qiu Suizheng
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The Effects of Ion Irradiation on the Microstructure and Hydrogen Permeation Properties of Fe-Al/Al2O3 Coatings
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deleteLi, Changzheng; Shu, Rui; Li, Yinghong; Zhang, Guoliang; Wang, Long; Liu, Xiang; Ren, Qisen; Nie, Lihong; Zhang, Shaohong
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Phase-Field Simulation of Recrystallization in High Burnup UO2
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deleteChen, Xingyu; Ma, Jianyi; Wang, Qingyu; Zhang, Tian
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Estimation of Effective Thermal Conductivity in U3Si2-al Dispersion Fuels with Fission Gas Bubbles
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deleteLi, Yong; Cao, Zhiwei; Xu, Miaomiao; Li, Qiang; Wang, Gang; Lin, Zhikang
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Impact of Aluminium in High-temperature and High-pressure Water on the Oxide Films of 304L Stainless Steel for Nuclear Power Plants
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deleteCai Xiangyu; Chen Yongxing; Chen Jun; Song Lijun; Cai Shengli; Tian Wei; Dai Yangcong; Zhao Peng; Chen Hongjie; Hou Zhenyu
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Experimental Study on Irradiation Hardening of Nickel-Based Alloy
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deleteCui, Wen-dong; Nie, Jun-feng; He, Lei; Chen, Jun-yu; Lin, Pan-dong
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High-Fidelity Source Term Calculation Approach for Liquid-Fueled Molten Salt Reactors via Multi-physics Coupling
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deleteXuan, Xiaojie; Xia, Shaopeng; Cheng, Maosong
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The Primary Analysis of Flow Blockage Accident of Irradiation Device in Research Reactor
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deleteXie, Xuanting; Guo, Yuchuan; Guo, Xiaoyu; Wang, Guanbo; Guo, Simao; Tang, Bin; Fan, Jie; Yang, Yan; Wang, Zhenpeng
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Optimization Study and Validation of Reaching Criticality of HPR1000 Unit
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deleteLiu, Bo; Cai, Dechang; Xu, Xingxing; Zhu, Yuxiang; Zhao, Changyou; Li, Zhijun
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Fuel Washout from Defective Fuel Rod in PWR
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deleteFu, Pengtao; Dai, Mingliang; Li, Zhijun; Zhang, Xiaoqian
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Measurement of Key Nuclides in Thorium-Based Fuels Based on White Light Neutron Sources
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deleteLuo, Yongjie; Wu, Jianhui; Cai, Xiangzhou; Hu, Jifeng; Chen, Jingen
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Study on Li Concentration and pH Value Limit of CZ Zirconium Alloy
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deleteWu, XinFeng; Chen, LiuTao; Wang, Xu; Shi, Lin; Zhang, Guoliang
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The Influence of Temperature on the Deformation Mechanism of CZ1 Alloy Investigated by In-Situ EBSD Technique
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deleteLv, Qingyang; Lin, Weitong; Hu, Haixiang; Chen, Liutao; Hu, Jing
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Orderly Grabbing and Disassembly Technology of Automatic Charging System for New Fuel in High Temperature Gas Cooled Reactor Development and Practice
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deleteLei Weijun; Xin, Guan; Jin, Shi; Lin, Ye; Ping, Liu; Shichun, Zhang
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Study on the Stress Relaxation Analysis Method of the Nickel-Based 718 Alloy Grid Spring
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deleteTang, Yingzhuo; Zhao, Shufeng; Sun, Jingya; Wang, Zhenxing; Zhao, Jingjing; Gan, Fujun
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