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Xianping Zhong, Pengya Guo, Xiaolong Zhang, Muhammad Saeed, Haoran Ma, Jianqi Huang, Jiyang Yu.Development of a seven-region lumped parameter nonlinear dynamic model for U-tube recirculation nuclear steam generator.Annals of Nuclear Energy. V174.2022
Zhong, Xianping; Zhang, Xiaolong; Saeed, Muhammad; Li, Zhongchun; Yu, Jiyang.Comparative study on water thermodynamic property functions of TRACE code.ANNALS OF NUCLEAR ENERGY. V147.2020
Zhong, Xianping; Yu, Jiyang; Zhang, Xiaolong; Saeed, Muhammad; Li, Yi; Chen, Zhihui; Tang, Bin; Sun, Yan; Huang, Tao.Development of a Lumped Parameter Dynamic Degassing Model for Spray-Heating Degasser and Its Application in the Pressurizer of a Pressurized Water Reactor.NUCLEAR TECHNOLOGY. V207(2). pp228-246.2021
Saeed, Muhammad; Zhong, Xianping; Yu, Jiyang; Zhang, Xiaolong; Abdalla, Aniseh Ahmed Atef.Sensitivity Analysis of Some Key Factors on Turbulence Models for Hydrogen Diffusion Using HYDRAGON Code.FRONTIERS IN ENERGY RESEARCH. V8.2020
Zhang, Chunhui; Yu, Jiyang; Zhong, Xianping; Saeed, Muhammad.A Numerical Investigation on Gaseous Stratification Break-Up Phenomenon of Air Fountain Experiment by Code_Saturne.FRONTIERS IN ENERGY RESEARCH. V7.2019
Zhang, Xiaolong; Yu, Jiyang; Huang, Tao; Jiang, Guangming; Zhong, Xianping; Saeed, Muhammad.An improved method for hydrogen deflagration to detonation transition prediction under severe accidents in nuclear power plants.INTERNATIONAL JOURNAL OF HYDROGEN ENERGY. V44(21). pp11233-11239.2019
Zhong, Xianping; Zhang, Xiaolong; Yu, Jiyang; Saeed, Muhammad; Li, Yi; Chen, Zhihui; Tang, Bin; Sun, Yan.Development of an improved non-equilibrium multi-region model for pressurized water reactor pressurizer.ANNALS OF NUCLEAR ENERGY. V126. pp133-141.2019
Zhong, Xianping; Yu, Jiyang; Yan, Shengyu; Saeed, Muhammad; Li, Yaodong.Analysis of wall temperature jump of China Generation IV SFR Steam Generator.ANNALS OF NUCLEAR ENERGY. V114. pp510-517.2018
Zhong, Xianping; Yu, Jiyang; Guo, Xiaoyu; Saeed, Muhammad.Analysis of degassing time of pressurized water reactor pressurizer.NUCLEAR ENGINEERING AND DESIGN. V328. pp301-308.2018
Zhang, Xiaolong; Tseng, Peichi; Saeed, Muhammad; Yu, Jiyang.A CFD-based simulation of fluid flow and heat transfer in the Intermediate Heat Exchanger of sodium-cooled fast reactor.ANNALS OF NUCLEAR ENERGY. V109. pp529-537.2017
Saeed, Muhammad; Yu, Ji-Yang; Abdalla, Aniseh Ahmed Atef; Zhong, Xian-Ping; Ghazanfar, Mahmood Ahmad.An assessment of k-epsilon turbulence models for gas distribution analysis.NUCLEAR SCIENCE AND TECHNIQUES. V28(10).2017
Yu, Jiyang; Hou, Bingxu; Lelyakin, Alexander; Xu, Zhanjie; Jordan, Thomas.Gas detonation cell width prediction model based on support vector regression.NUCLEAR ENGINEERING AND TECHNOLOGY. V49(7). pp1423-1430.2017
Saeed, Muhammad; Yu, Jiyang; Abdalla, Aniseh Ahmed Atef; Hou, Bingxu; Hussain, Ghulam; Zhong, Xianping.The effect of turbulence modeling on hydrogen jet dispersion inside a compartment space using the HYDRAGON code.JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY. V54(7). pp725-732.2017
Saeed, Muhammad; Yu, Jiyang; Zhong Xianping; Hou, Bingxu; Zhang, Xiaolong; Ghazanfar, Mahmood Ahmad; Liu Guangyin; Yang, Chunzhen.EFFECT OF MESH RESOLUTION AND BUOYANCY-DRIVEN FLOWS ON THE k - epsilon TURBULENCE MODELS USING THE HYDRAGON CODE.PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 8. V.2017
Zhang, Xiaolong; Tseng, Peichi; Yu, Jiyang; Saeed, Muhammad.A CFD-BASED OPTIMIZATION DESIGN OF FLOW DISTRIBUTION DEVICE IN THE LOWER PLENUM OF INTERMEDIATE HEAT EXCHANGER OF SFR.PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 8. V.2017
Zhong, XP ; Yu, JY ; Saeed, M; Yang, CZ; Zhang, XLAnalysis of Hydrodynamic Characteristic in Straight Tube Sodium-Heated Once-Through Steam Generator of CFR600. PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 62017
Saeed, M.; Yu Jiyang; Hou, B. X.; Abdalla, Aniseh A. A.; Zhang Chunhui.NUMERICAL SIMULATION OF HYDROGEN DISPERSION INSIDE A COMPARTMENT USING HYDRAGON CODE.PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4. V.2016
Li Zhongchun; Song Xiaoming; Jiang Shengyao; Yu Jiyang; Mamoru Ishii.Experimental Investigation on Motion Characteristics of Relative Large Bubble.Nuclear Power Engineering. V36(1). pp161-164.2015
Li Zhongchun; Song Xiaoming; Jiang Shengyao; Yu Jiyang.Numerical investigation on lateral migration and lift force of single bubble in simple shear flow in low viscosity fluid using volume of fluid method.NUCLEAR ENGINEERING AND DESIGN. V274. pp154-163.2014
Abdalla, Aniseh A. A.; Yu, Jiyang; Alrawashdeh, Mohammed.APPLICATION OF SOME TURBULENCE MODELS TO SIMULATE BUOYANCY-DRIVEN FLOW.PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 4. V.2014
Gao, Lijun; Chen, Bingde; Xiao, Zhong; Jiang, Shengyao; Yu, Jiyang.MODELING THE IRRADIATION SWELLING OF UO2 AT THE FUEL PELLET RIM.PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1. V.2014
Li Ran; Yu Jiyang.DEVELOPMENT OF PCCSAP-3D CODE FOR PASSIVE CONTAINMENT-MODELS OF NONCONDENSABLE GASES, AEROSOLS AND FISSION PRODUCTS.PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3. V.2014
Gao, Lijun; Chen, Bingde; Xiao, Zhong; Jiang, Shengyao; Yu, Jiyang.Pore pressure calculation of the UO2 high burnup structure.NUCLEAR ENGINEERING AND DESIGN. V260. pp11-15.2013
Abdalla, Aniseh Ahmed Atef; Yu, Jiyang; Yang, Yongwei.Thermal-hydraulic analysis of LBE spallation target for accelerator-driven systems.PRAMANA-JOURNAL OF PHYSICS. V80(1). pp89-103.2013
Wu, Dan; Yu, Hongxing; Yu, Junchong; Yu, Jiyang.Reflooding characteristics investigation and predicted models improvement for the pressurized water reactor with the tight lattice core design.NUCLEAR ENGINEERING AND DESIGN. V249. pp335-347.2012
Gao, Lijun; Pang, Hua; Chen, Bingde; Jiang, Shengyao; Yu, Jiyang; Xiao, Zhong.PROBABILITY ANALYSIS OF THE FUEL MICROSPHERE DISTRIBUTION OF DISPERSION-TYPE NUCLEAR FUEL PLATES.PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 5. V.2012
Li, Jie; Yu, Junchong; Jiang, Guangming; Yu, Jiyang.ASSESSMENT OF PERFORMANCE OF TURBULENCE MODELS OF CFX IN PREDICTING SUPERCRITICAL WATER HEAT TRANSFER IN A VERTICAL TUBE.PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 4. V. pp505-509.2012
Li, ZhongChun; Yu, JiYang; Song, XiaoMing.STABILITY ANALYSIS OF A SUPERCRITICAL WATER NATURAL CIRCULATION LOOP.PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 3. V. pp687-696.2012
Wu, Dan; Yu, Hongxing; Yu, Junchong; Li, Jie; Yu, Jiyang.DEVELOPMENT OF A NEW HEAT TRANSFER MODEL NEAR THE QUENCH FRONT IN THE REFLOODING PHASE OF A TIGHT LATTICE.PROCEEDINGS OF THE 20TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING AND THE ASME 2012 POWER CONFERENCE - 2012, VOL 3. V. pp227-234.2012
Yu, Jiyang; Che, Shuwei; Li, Ran; Qi, Bingxue.Analysis of Ledinegg flow instability in natural circulation at supercritical pressure.PROGRESS IN NUCLEAR ENERGY. V53(6). pp775-779.2011
Yu, Jiyang; Jia, Baoshan; Wu, Dan; Wang, Daling.Optimization of heat transfer coefficient correlation at supercritical pressure using genetic algorithms.HEAT AND MASS TRANSFER. V45(6). pp757-766.2009
Yu, Jiyang; Liu, Haiyu; Jia, Baoshan.Sub-channel analysis of CANDU-SCWR and review of heat-transfer correlations.PROGRESS IN NUCLEAR ENERGY. V51(2). pp246-252.2009
Yu Jiyang; Wang Songtao; Jia Baoshan.Development of sub-channel analysis code for CANDU-SCWR.PROGRESS IN NUCLEAR ENERGY. V49(4). pp334-350.2007
Yu, Jiyang; Mao, Wenlong; Ha, Baoshan; Rao, Yanfei; Ruan, Yangqiang.Thermal hydraulic analysis of the thorium-based advanced CANDU Reactor fuel channel.PROGRESS IN NUCLEAR ENERGY. V48(6). pp559-568.2006
Yu, JY; Wang, K; You, SB; Jia, BS; Shen, SF; Shi, G; Rayman, S; Ruan, YQ.Thorium fuel cycle of a thorium-based advanced nuclear energy system.PROGRESS IN NUCLEAR ENERGY. V45(1). pp71-83.2004
俞冀阳.谈“核”容易.中国核电.V14（2). pp289-291.2021
俞冀阳.“安全兜底”——第三代核电技术的精髓.农村电工.V27（1). pp61.2019
俞冀阳.Q&A 中子注量率、中子通量.中国核电.V11（3). pp291.2018
俞冀阳.如何在核能项目中求得公众沟通最优化.中国核电.V11（3). pp292-295.2018
俞冀阳.电吹风的辐射真的很大吗?.中国核电.V11（3). pp306.2018
俞冀阳.公众沟通中的核心理学.中国核电.V11（1). pp120-123.2018
侯炳旭,俞冀阳,徐沾杰,江光明.利用支持向量回归对燃爆单元宽度进行预测的方法研究.原子能科学技术.V51（6). pp1024-1029.2017
侯炳旭,俞冀阳,徐沾杰,江光明,邹志强.利用高斯过程回归对燃爆单元宽度的预测方法研究.核动力工程.V38（2). pp72-77.2017
侯炳旭,俞冀阳,江光明,陈彬.基于HYDRAGON程序对安全壳壁面水蒸气冷凝现象的数值模拟.核动力工程.V37（4). pp81-86.2016
侯炳旭,俞冀阳,钟先平,江光明,邹志强.氢气复合器算例数值模拟结果的不确定性分析和敏感性分析.核动力工程.V37（3). pp80-86.2016
侯炳旭,俞冀阳,Dorothée Sénéchal,江光明,闵皆昇.采用低马赫数方法对空气射流破坏氦气分层现象的数值模拟.核动力工程.V36（6). pp61-66.2015
李仲春,宋小明,姜胜耀,俞冀阳,Mamoru Ishii.静水中较大气泡运动特性实验研究.核动力工程.V36（1). pp161-164.2015
高利军,姜胜耀,陈炳德,肖忠,俞冀阳.考虑静水压力的HBS辐照肿胀本构关系开发及验证.原子能科学技术.V48（8). pp1381-1385.2014
李松蔚,张虹,姜胜耀,俞冀阳.竖直环管内低压水过冷沸腾数值模拟研究.核动力工程.V35（1). pp46-51.2014
李捷,江光明,俞冀阳,于俊崇.CFX中湍流模型用于分析超临界水传热的适用性评价.原子能科学技术.V48（1). pp67-73.2014
吴丹,余红星,于俊崇,俞冀阳.稠密棒束通道内骤冷前沿附近壁面放热模型研究.核动力工程.V34（4). pp33-37.2013
侯炳旭,俞冀阳.大型九对角线性方程组的MG-SIP算法研究.原子能科学技术.V47（6). pp975-982.2013
艾尼塞,俞冀阳,杨永伟.PDS-XADS散裂靶热工水力分析.原子能科学技术.V47（2). pp260-265.2013
齐炳雪,俞冀阳.RELAP5程序的临界流模型分析.核安全.V（4). pp63-66+2.2012
高利军,陈炳德,姜胜耀,肖忠,俞冀阳,张林,李垣明.弥散型燃料板的辐照起泡机理分析.原子能科学技术.V46（S2). pp819-825.2012
齐炳雪,俞冀阳.超临界水冷堆的安全分析.原子能科学技术.V46（6). pp669-673.2012
熊挺,闫晓,俞冀阳,曾小康,肖泽军.并行双通道内超临界水流动不稳定性数值分析.核动力工程.V33（2). pp62-65.2012
李松蔚,张虹,姜胜耀,俞冀阳.棒束定位格架两相CFD模拟方法研究.核动力工程.V33（2). pp92-96.2012
俞冀阳,王松涛,张向宇,毛文龙.燃料棒内氦气压力无损检测的数值模拟.核科学与工程.V（3). pp193-197.2007
王松涛,俞冀阳,廉海波,毛文龙.钍基先进坎杜堆子通道分析.核动力工程.V（4). pp13-15+116.2007
毛文龙,游松波,俞冀阳.TACR燃料通道的子通道分析.核科学与工程.V（3). pp204-208.2006
徐良旺,贾宝山,俞冀阳.基于热胀冷缩原理的TACR压力管与排管间非能动热开关设计.核动力工程.V（1). pp58-61+65.2006
滕雁,俞冀阳,宗波,王建平.核反应堆退役初期辐射特性的探讨.核安全.V（3). pp34-37.2005
王根来,俞冀阳.关于室内氡辐射防护的探讨.核安全.V（2). pp54-56+59.2005
俞冀阳,俞尔俊,贾宝山.核反应堆非能动余热排出系统分析.核安全.V（4). pp35-39.2004
游松波,俞冀阳,杨高升.钍基先进核能系统压力管与排管之间的非能动热开关设计.核动力工程.V（3). pp260-263.2004
周文俊,贾宝山,俞冀阳.压力管式反应堆非能动余热排出系统方案研究.核技术.V（7). pp523-526.2003
俞冀阳,贾宝山.一种反应堆非能动余热排出系统的方案设计.核科学与工程.V（1). pp32-38.2003
冷贵君,余红星,俞冀阳,贾宝山.先进堆非能动安全壳热工水力瞬态分析及研究.核动力工程.V（S1). pp59-65.2002
杨珏,贾宝山,俞冀阳.面向对象的LU-SGS流场计算程序设计.计算机工程.V（12). pp235-236+281.2002
杨珏,贾宝山,俞冀阳.简谐海洋条件下堆芯冷却剂系统自然循环能力分析.核科学与工程.V（3). pp199-203+209.2002
杨珏,贾宝山,俞冀阳.海洋条件下冷却剂系统自然循环仿真模型.核科学与工程.V（2). pp125-129.2002
俞冀阳,李坤,贾宝山.AC600非能动安全壳冷却系统长期效应分析.核动力工程.V（3). pp60-62.2002
俞冀阳,贾宝山.AC600非能动安全壳冷却系统冷凝传热系数评价.核动力工程.V（3). pp22-26.1999
俞冀阳,贾宝山,郑成武.非能动安全壳冷却系统的一维分析程序PCCSAC-1D.核动力工程.V（6). pp73-77.1998
李仲春,宋小明,姜胜耀,俞冀阳,Mamoru Ishii.低粘剪切流场中相间升力模型研究.中国核学会核能动力分会反应堆热工流体专业委员会.第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会论文集. pp213-218.2015
艾尼塞,俞冀阳,杨永伟.PDS—XADS散裂靶热工水力分析.中国核学会.中国核科学技术进展报告（第二卷）——中国核学会2011年学术年会论文集第3册（核能动力分卷（下））. pp493-501.2011
王侃,余纲林,沈华韵,俞冀阳,李林森,李泽光,马纪敏,李松阳,刘井泉,柴晓明,黄世恩,宫兆虎,李满仓,赵丈博,张鹏.数字反应堆平台建设的研究进展.清华大学工程物理系.第三届反应堆物理与核材料学术研讨会论文集. pp8.2007
王侃,余纲林,沈华韵,俞冀阳,李林森,李泽光,马纪敏,李松阳,刘井泉,柴晓明,黄世恩,宫兆虎,李满仓,赵文博,张鹏.数字反应堆平台建设的研究进展.清华大学工程物理系.第三届反应堆物理与核材料学术研讨会论文摘要集. pp8.2007
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