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Proceedings Papers

Seismic Analysis of Fuel Transfer Tube Gate Valve

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Su Ziwei, Zhang Xin
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89869
https://doi.org/10.1115/ICONE29-89869
View Paper titled, Seismic Analysis of Fuel Transfer Tube Gate Valve
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Topics: Design, Fuels, Gates (Closures), Seismic analysis, Valves
Proceedings Papers

A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank

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Chengzhuo Yang, Thomas Metais, Zihao Zheng, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A070, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93230
https://doi.org/10.1115/ICONE29-93230
View Paper titled, A Comparative Approach of a Seismic Response Analysis Based on Housner Model and Added Mass Model for a Nuclear Water Storage Tank
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Topics: Water, Water storage, Sloshing, Fluid structure interaction, Center of mass, Convection, Displacement, Dynamic response, Finite element analysis, Finite element model
Proceedings Papers

Development and Verification of New Drum Filter Equipment for Nuclear Power Plants

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Huang Xiaojie, Lin Yishan, Xie Honghu, Li Yanqing, Yang Jinchun
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92243
https://doi.org/10.1115/ICONE29-92243
View Paper titled, Development and Verification of New Drum Filter Equipment for Nuclear Power Plants
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Topics: Cooling, Engineering prototypes, Filters, Nuclear power stations, Safety, Seismic analysis
Proceedings Papers

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

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Gang Rong, He Zhu, Yi Yang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91753
https://doi.org/10.1115/ICONE29-91753
View Paper titled, Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor
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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells
Proceedings Papers

Seismic Response Analysis of Pile Foundation of an Underground Storage Facility of Nuclear Power Project

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Dongyang Wang, Xiaoying Sun, Ziqiao Liu, Yingying Gan
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89349
https://doi.org/10.1115/ICONE29-89349
View Paper titled, Seismic Response Analysis of Pile Foundation of an Underground Storage Facility of Nuclear Power Project
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Topics: Nuclear power, Pilings (Building), Seismic analysis, Soil, Underground storage
Proceedings Papers

Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation

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Oleksii Ishchenko, Vladislav Filonov, Yaroslav Dubyk
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A085, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65756
https://doi.org/10.1115/ICONE28-65756
View Paper titled, Dynamic Model of the VVER-1000 Reactor for Seismic and LB LOCA Evaluation
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Topics: Accidents, Cavitation, Computational fluid dynamics, Coolants, Design, Dynamic analysis, Dynamic models, Dynamic response, Dynamic stability, Dynamics (Mechanics)
Proceedings Papers

Research and Application of Different Seismic Analysis Methods in Nuclear Power Equipment

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Xuan Huang, Furui Xiong, Shuai Liu, Huanhuan Qi, Qian Huang, Ke Zhang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A024, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64605
https://doi.org/10.1115/ICONE28-64605
View Paper titled, Research and Application of Different Seismic Analysis Methods in Nuclear Power Equipment
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Topics: Nuclear power, Seismic analysis
Proceedings Papers

Seismic Analysis and Design of HPR1000 Degassing Tower Liquid Cooler

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Junjie Dang, Wenmo Li, Chunming Wang, Xingling Tang
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A053, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82609
https://doi.org/10.1115/ICONE26-82609
View Paper titled, Seismic Analysis and Design of HPR1000 Degassing Tower Liquid Cooler
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Topics: Design, Seismic analysis, Boron, Earthquakes, Finite element analysis, Nuclear power stations, Security
Proceedings Papers

Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator

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Feng-chun Cai, Xian-hui Ye, Qian Huang, Wenzheng Zhang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81279
https://doi.org/10.1115/ICONE26-81279
View Paper titled, Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator
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Topics: Boilers, Failure, Probability, Stress, Nonlinear systems, Nuclear reactor coolants, Plasticity, Safety, Seismic analysis, Stress analysis (Engineering)
Proceedings Papers

Decoupling Method of Sloshing Water in PCCWST of Large-Scale Advanced Passive PWR Nuclear Power Plant

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Boyu Han, Fang Yuan, Zufeng Xia, Honghui Ge, Shenghua Liu, Xiaowen Wang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A078, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67011
https://doi.org/10.1115/ICONE25-67011
View Paper titled, Decoupling Method of Sloshing Water in PCCWST of Large-Scale Advanced Passive PWR Nuclear Power Plant
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Topics: Nuclear power stations, Pressurized water reactors, Sloshing, Water, Modeling, Seismic analysis, Containment, Cooling, Errors, Fluids
Proceedings Papers

Seismic Performance of PCS Water Storage Tank Considering Fluid-Structure Interaction

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Hongliang Gou, ZiDuan Shang, Yugang Sun, Meng Chu, Honghui Ge
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66338
https://doi.org/10.1115/ICONE25-66338
View Paper titled, Seismic Performance of PCS Water Storage Tank Considering Fluid-Structure Interaction
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Topics: Fluid structure interaction, Water storage, Water, Sloshing, Design, Dynamic response, Finite element model, Modal analysis, Shear (Mechanics), Springs
Proceedings Papers

Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake

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Ling Yun, Li Lei, Xue Rongjun, Qian Hao, Ge Honghui, Shang Ziduan
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A083, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67136
https://doi.org/10.1115/ICONE25-67136
View Paper titled, Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake
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Topics: Earthquakes, Fluid structure interaction, Numerical analysis, Spent nuclear fuels, Storage, Finite element analysis, Water, Sloshing, Computational fluid dynamics, Concretes
Proceedings Papers

CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China

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Libing Zhu, Jie Ding, Qin Zhou, Yunqing Zhou, Fujun Gan, Junqiang Lu, Yixiong Zheng, Jiwei Li, Yang Ding, Qifeng Zeng, Song Liu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66700
https://doi.org/10.1115/ICONE25-66700
View Paper titled, CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China
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Topics: China, Fuels, Manufacturing, Pressurized water reactors, Irradiation (Radiation exposure), Alloys, Cladding systems (Building), Design, Fuel rods, Reliability
Proceedings Papers

Seismic Analysis for an Explosion-Proof Valve Used in Nuclear Power Plant

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Juan Luo, Jiacheng Luo, Lei Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A077, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66995
https://doi.org/10.1115/ICONE25-66995
View Paper titled, Seismic Analysis for an Explosion-Proof Valve Used in Nuclear Power Plant
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Topics: Explosions, Nuclear power stations, Seismic analysis, Valves, Safety, Stress, Deformation, Design, Earthquakes, Finite element methods
Proceedings Papers

Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing

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Hongda Liu, Daogang Lu, Xiaoxuan Li, Xiaojia Zeng, Guangdong Bao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66111
https://doi.org/10.1115/ICONE25-66111
View Paper titled, Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing
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Topics: Seismic analysis, Sloshing, Sodium fast reactors, Vessels, Water, Waves, Fast neutron reactors, Pressure, Design, Earthquake resistant design
Proceedings Papers

Safety Enhancement Study of CAP1400 Spent Fuel Storage Racks

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Xiaoming He, Ziqiang Zhu, Changlei Shao, Ran Huang
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T02A001, June 26–30, 2017
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2017-3164
https://doi.org/10.1115/NUCLRF2017-3164
View Paper titled, Safety Enhancement Study of CAP1400 Spent Fuel Storage Racks
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Topics: Safety, Spent fuel storage, Cooling, Neutrons, Storage, China, Computational fluid dynamics, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressurized water reactors
Proceedings Papers

The Effect on the Support Seismic Loads of Primary Equipment With Different Reactor Coolant Pump

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Ye Xianhui, Cai Fengchun, Lan Bin, Zhang Yixiong
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A002, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60091
https://doi.org/10.1115/ICONE24-60091
View Paper titled, The Effect on the Support Seismic Loads of Primary Equipment With Different Reactor Coolant Pump
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Topics: Nuclear reactor coolants, Pumps, Stress, Computational methods, Economics , Nuclear design, Safety, Seismic analysis
Proceedings Papers

Seismic Analysis and Design Upgrade of Condensate Storage Tanks

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Daniel Moreno, John O’Sullivan, Tsiming Tseng
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A016, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60741
https://doi.org/10.1115/ICONE24-60741
View Paper titled, Seismic Analysis and Design Upgrade of Condensate Storage Tanks
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Topics: Condensed matter, Design, Seismic analysis, Storage tanks, Earthquakes, Nuclear power stations, Stress, Shear (Mechanics), Anchor bolts, Anchorage
Proceedings Papers

Confirmation of Seismic Integrity of HTTR Against 2011 Great East Japan Earthquake

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Masato Ono, Kazuhiko Iigaki, Yosuke Shimazaki, Atsushi Shimizu, Hiroyuki Inoi, Daisuke Tochio, Shimpei Hamamoto, Tetsuo Nishihara, Shoji Takada, Kazuhiro Sawa, Toshinari Kondo, Keidai Kojima
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60571
https://doi.org/10.1115/ICONE24-60571
View Paper titled, Confirmation of Seismic Integrity of HTTR Against 2011 Great East Japan Earthquake
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Topics: Earthquakes, Inspection, Instrumentation, Very high temperature reactors, Damage, Earthquake resistant design, High temperature, Industrial research, Maintenance, Nuclear power
Proceedings Papers

Evaluation of Damaging Effects on a NPP Integrity Subjected to Beyond Design Earthquake

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Rosa Lo Frano, Giuseppe Forasassi
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A018, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16469
https://doi.org/10.1115/ICONE21-16469
View Paper titled, Evaluation of Damaging Effects on a NPP Integrity Subjected to Beyond Design Earthquake
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Topics: Design, Earthquakes, Nuclear power stations, Containment, Failure, Bearings, Concretes, Constitutive equations, Containment buildings, Damage