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Proceedings Papers

Numerical Simulation Analysis of the Air Temperature Measurement Scheme for Big Space in Containment

Tiexin Fan, Xianbin Zeng, Qi Niu, Bin Tu, Dongshan Huang, Zhengjie Liu
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A065, August 8–12, 2022
Paper No: ICONE29-93513
DOI: https://doi.org/10.1115/ICONE29-93513
View Paper titled, Numerical Simulation Analysis of the Air Temperature Measurement Scheme for Big Space in Containment
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Topics: Computational fluid dynamics, Computer simulation, Containment, Design, Temperature measurement, Temperature, Computer software, Computer-aided design, Nuclear power stations, Accidents
Proceedings Papers

Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

NingYan Sun, ShiChang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 8–12, 2022
Paper No: ICONE29-91727
DOI: https://doi.org/10.1115/ICONE29-91727
View Paper titled, Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods
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Topics: Fuels, Geometry, Computer-aided design, Modeling, Particulate matter, Monte Carlo methods
Proceedings Papers

Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC

Pengfei Shen, Jingang Liang, Shichang Liu, Kan Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A075, August 8–12, 2022
Paper No: ICONE29-93103
DOI: https://doi.org/10.1115/ICONE29-93103
View Paper titled, Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC
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Topics: Computer-aided design, Engineering simulation, Geometry, Nuclear reactors, Particulate matter, Physics, Simulation, Transport processes, Weight (Mass)
Proceedings Papers

Development of Design Support System for Piping Route and Differential Pressure Flowmeter by Three-Dimensional Fluid Analysis

Takatsugu Miura, Kingo Igarashi, Tomoyuki Hosaka, Takumi Kitagawa, Tatsurou Yashiki, Yuki Itabayashi, Hirotsugu Suzuki, Takashi Nakahara, Junichi Kitamura, Tadashi Sano
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A022, August 4–5, 2020
Paper No: ICONE2020-16745
DOI: https://doi.org/10.1115/ICONE2020-16745
View Paper titled, Development of Design Support System for Piping Route and Differential Pressure Flowmeter by Three-Dimensional Fluid Analysis
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Topics: Design, Flowmeters, Fluids, Pipes, Pressure, Flow (Dynamics), Flow measurement, Computer-aided design, Visualization, Engineers
Proceedings Papers

3D Immersive Display Application for Nuclear Education and Public Acceptance

Bing Lam Luk, Miu-Ling Lam, Ting-Hsuan Chen, Jiyun Zhao, Suet Man Tsui, Ching-Chang Chieng
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A005, July 22–26, 2018
Paper No: ICONE26-81161
DOI: https://doi.org/10.1115/ICONE26-81161
View Paper titled, 3D Immersive Display Application for Nuclear Education and Public Acceptance
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Topics: Education, Nuclear power, Nuclear reactors, Carbon, Containment buildings, Nuclear power stations, Boilers, China, Computer-aided design, Containment
Proceedings Papers

Research on Structural Design and Analysis of S-CO 2 Turbine Impeller

Jun Wu, Can Ma, Chunhui Dai, Zhenxing Zhao, Lu Dai, Zhouyang Liu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A008, July 22–26, 2018
Paper No: ICONE26-81267
DOI: https://doi.org/10.1115/ICONE26-81267
View Paper titled, Research on Structural Design and Analysis of S-CO 2 Turbine Impeller
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Topics: Impellers, Structural design, Supercritical carbon dioxide, Turbines, Deformation, Stress, Safety, Blades, Brayton cycle, Carbon
Proceedings Papers

RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility

Mohammad A. Hawila, Karen Vierow Kirkland
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A008, July 22–26, 2018
Paper No: ICONE26-81119
DOI: https://doi.org/10.1115/ICONE26-81119
View Paper titled, RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility
Click here to open pdf in another window PDF for RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility
Topics: Computational fluid dynamics, Pumps, Testing, Turbochargers, Test facilities, Design, Engineering simulation, Nuclear power stations, Simulation, Turbines
Proceedings Papers

Advances in FEMN: The Code for Nuclear Noise Analysis Based on ICEM-CFD

Baoxin Yuan, Herong Zeng, Wankui Yang, Songbao Zhang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A006, July 22–26, 2018
Paper No: ICONE26-81169
DOI: https://doi.org/10.1115/ICONE26-81169
View Paper titled, Advances in FEMN: The Code for Nuclear Noise Analysis Based on ICEM-CFD
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Topics: Computational fluid dynamics, Ferromanganese, Noise (Sound), Geometry, Finite element methods, Neutrons, Physics, Computer software, Computer-aided design, Finite element analysis
Proceedings Papers

Development of a Device for Detecting Helium Leaks From Canisters: Part 2 — Numerical Analysis of Temperature Behavior During Gas Leaks From a Canister of a 1/4.5 Scale Cask Model

Kosuke Shimizu, Hirofumi Takeda, Masanori Goto
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A037, July 22–26, 2018
Paper No: ICONE26-81417
DOI: https://doi.org/10.1115/ICONE26-81417
View Paper titled, Development of a Device for Detecting Helium Leaks From Canisters: Part 2 — Numerical Analysis of Temperature Behavior During Gas Leaks From a Canister of a 1/4.5 Scale Cask Model
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Topics: Helium, Leakage, Numerical analysis, Temperature, Computational fluid dynamics, Heat transfer, Pressure, Sensors, Concretes, Computer software
Proceedings Papers

Mechanical Characteristics of Nuclear Main Steam Line Penetration Fabricated by Electric Melting Additive Manufacturing

Xiaoming He, Xiaoning Zhang, Yongdong Wang, Yiqing Wang, Dong Ning
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A035, July 2–6, 2017
Paper No: ICONE25-66332
DOI: https://doi.org/10.1115/ICONE25-66332
View Paper titled, Mechanical Characteristics of Nuclear Main Steam Line Penetration Fabricated by Electric Melting Additive Manufacturing
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Topics: Additive manufacturing, Mechanical properties, Melting, Steam, Manufacturing, Aerospace industry, Biomedicine, Computer-aided design, Economics , Nuclear power stations
Proceedings Papers

Isogeometric Analysis of Pipe System in Nuclear Power Plant

Le Shen, Yang Xia
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A015, July 2–6, 2017
Paper No: ICONE25-66147
DOI: https://doi.org/10.1115/ICONE25-66147
View Paper titled, Isogeometric Analysis of Pipe System in Nuclear Power Plant
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Topics: Nuclear power stations, Pipes, Simulation, Computer-aided design, Displacement, Geometry, Pipeline systems, Approximation, Boundary-value problems, B-splines
Proceedings Papers

Design and Implementation of Visual Design Datacenter for Nuclear Power Plant

Lu Hui, Liu Zhong, Niu Bo, Zhang Lin, Rong Hui, Hu Chunping, Liu Yu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A005, July 2–6, 2017
Paper No: ICONE25-66171
DOI: https://doi.org/10.1115/ICONE25-66171
View Paper titled, Design and Implementation of Visual Design Datacenter for Nuclear Power Plant
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Topics: Design, Nuclear power stations, Computer software, Computer-aided design, Data fusion
Proceedings Papers

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

Kun Xu, Minyou Ye, Yuntao Song, Mingzhun Lei, Shifeng Mao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A035, July 2–6, 2017
Paper No: ICONE25-67291
DOI: https://doi.org/10.1115/ICONE25-67291
View Paper titled, Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket
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Topics: Ceramics, Helium, Lithium, Design, China, Energy generation, Tokamaks, Vacuum, Vessels, Bridges (Structures)
Proceedings Papers

Development of Numerical Simulation Method for Melt Relocation Behavior in Nuclear Reactors: Validation of Applicability for Actual Core Support Structures

Susumu Yamashita, Kazuyuki Tokushima, Masaki Kurata, Kazuyuki Takase, Hiroyuki Yoshida
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A026, June 26–30, 2016
Paper No: ICONE24-60453
DOI: https://doi.org/10.1115/ICONE24-60453
View Paper titled, Development of Numerical Simulation Method for Melt Relocation Behavior in Nuclear Reactors: Validation of Applicability for Actual Core Support Structures
Click here to open pdf in another window PDF for Development of Numerical Simulation Method for Melt Relocation Behavior in Nuclear Reactors: Validation of Applicability for Actual Core Support Structures
Topics: Computer simulation, Nuclear reactors, High temperature, Solidification, Computer-aided design, Flow (Dynamics), Fluids, Fukushima nuclear disaster, Japan, 2011, Heat transfer, Nuclear power stations
Proceedings Papers

Design and Development of Virtual Assembly Prototype System for CLEAR-I

Leiming Shang, Zihui Yang, Jinbo Zhao, Tao He, Liqin Hu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T04A002, July 7–11, 2014
Paper No: ICONE22-30752
DOI: https://doi.org/10.1115/ICONE22-30752
View Paper titled, Design and Development of Virtual Assembly Prototype System for CLEAR-I
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Topics: Design, Engineering prototypes, Virtual assembly, Simulation, Virtual reality, China, Computer-aided design, Ergonomics, Manufacturing, Modeling
Proceedings Papers

The Status on Design Collaboration in ITER Chinese Domestic Agency

Shuqin Wu, Yuntao Song, Chao Xing, Delong Luo
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T14A002, July 29–August 2, 2013
Paper No: ICONE21-15159
DOI: https://doi.org/10.1115/ICONE21-15159
View Paper titled, The Status on Design Collaboration in ITER Chinese Domestic Agency
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Topics: Collaboration, Computer-aided design, Design
Proceedings Papers

Development of CAD-MCNP Interface Program “GEOMIT”

Hesham Nasif, Takashi Sato, Hidetsugu Morota, Akihiro Masui, Hideo Kitagawa
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 781-786, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54948
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54948
View Paper titled, Development of CAD-MCNP Interface Program “GEOMIT”
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Topics: Computer-aided design
Proceedings Papers

Primary Design and Operation Analysis of the ITER Transfer Cask System

Haitian Wang, Ge Li, Shijun Qin
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 489-494, May 17–21, 2010
Paper No: ICONE18-29030
DOI: https://doi.org/10.1115/ICONE18-29030
View Paper titled, Primary Design and Operation Analysis of the ITER Transfer Cask System
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Topics: Cables, China, Computer-aided design, Density, Design, Dimensions, Electric power generation, Engines, Fusion reactors, Hazards
Proceedings Papers

Democratization of 3D Applications in Nuclear Power Plants: Laser Scanning 3D Technology Implementation on Spanish PWRs

Xavier Jardi´, Jorge Anga´s
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 235-241, May 17–21, 2010
Paper No: ICONE18-30117
DOI: https://doi.org/10.1115/ICONE18-30117
View Paper titled, Democratization of 3D Applications in Nuclear Power Plants: Laser Scanning 3D Technology Implementation on Spanish PWRs
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Topics: Lasers, Nuclear power stations, Pressurized water reactors, Computer software, Computer-aided design, Containment, Cooling, Databases, Design, Elevations (Drawings)
Proceedings Papers

Development of the CAD/MCNP Automatic Conversion Code GEOMIT

Hesham R. Nasif, Fukuzo Masuda, Hiromasa Iida, Hidetsugu Morota, Satoshi Sato, Chikara Konno
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 807-814, July 12–16, 2009
Paper No: ICONE17-75229
DOI: https://doi.org/10.1115/ICONE17-75229
View Paper titled, Development of the CAD/MCNP Automatic Conversion Code GEOMIT
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Topics: Computer-aided design, Shapes, Solids, Density, Errors, Heat