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

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论文数42
被引数
期刊论文 42
发表时间
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Experiment Research and Data Benchmarking of YBS Critical Experiment Facility Lead Reactor CoreYBS临界实验设施铅反应堆堆芯的实验研究与数据基准测试
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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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基于贝叶斯方法对锆合金包壳中氢行为的不确定性量化与敏感性分析
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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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快堆燃料类型比较与选择初探
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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锆合金表面微弧氧化层的制备与性能
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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基于OpenMC代码和MOOSE框架的U-50Zr螺旋十字形燃料概念的中子-热耦合分析
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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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压水堆中螺旋燃料的氢扩散与沉积行为研究
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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离子辐照对Fe-Al/Al2O3涂层微观结构和氢渗透性能的影响
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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高燃耗UO2中再结晶的相场模拟
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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 BubblesU3Si2-al弥散燃料中含裂变气泡的有效热导率估计
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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铝在高温高压水中对核电站304L不锈钢氧化物膜的影响
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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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镍基合金辐照硬化的实验研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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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液态燃料熔盐反应堆高保真源项计算方法的多物理场耦合研究
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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研究反应堆中辐照装置流道堵塞事故的初步分析
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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 UnitHPR1000机组临界到达的优化研究及验证
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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压水堆中缺陷燃料棒的燃料流失
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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基于白光中子源对钍基燃料中关键核素的测量
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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 AlloyCZ锆合金中锂浓度和pH值限度的研究
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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温度对CZ1合金变形机制的影响研究：基于原位EBSD技术
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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高温气冷堆新燃料自动装卸料及拆解技术的研发与应用
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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镍基718合金栅弹簧应力松弛分析方法研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 4, ICONE 2025
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deleteTang, Yingzhuo; Zhao, Shufeng; Sun, Jingya; Wang, Zhenxing; Zhao, Jingjing; Gan, Fujun
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