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Proceedings Papers

An Optimal Design Method for Passive Residual Heat Removal System

Yuepeng Bi
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A015, August 8–12, 2022
Paper No: ICONE29-92518
DOI: https://doi.org/10.1115/ICONE29-92518
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Topics: Design methodology, Genetic algorithms, Heat
Proceedings Papers

Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant

Zhao Qingsen, Liang Junqin, Zhou Shuai, Chen Jie, Zeng Weipeng, Zhang Qiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A071, August 8–12, 2022
Paper No: ICONE29-93265
DOI: https://doi.org/10.1115/ICONE29-93265
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Topics: Condensers (steam plant), Cooling, Design methodology, Nuclear power stations, Pipes, Pressurized water reactors
Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022
Paper No: ICONE29-91474
DOI: https://doi.org/10.1115/ICONE29-91474
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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling
Proceedings Papers

Research on the Design Method of Nuclear Heat Exchanger Tube Based on Multi-Objective Optimization

G. M. Cao, L. Dai, Z. X. Zhao, T. He
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A007, August 8–12, 2022
Paper No: ICONE29-90436
DOI: https://doi.org/10.1115/ICONE29-90436
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Topics: Computer software, Design, Design methodology, Heat, Heat exchangers, Pareto optimization, Flow (Dynamics), Noise (Sound), Heat transfer, Simulation
Proceedings Papers

Study on Gas Entrainment From Unstable Drifting Vortexes on Liquid Surface

Moe Hirakawa, Yuichiro Kikuchi, Takaaki Sakai, Masaaki Tanaka, Hiroyuki Ohshima
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A091, July 22–26, 2018
Paper No: ICONE26-82477
DOI: https://doi.org/10.1115/ICONE26-82477
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Topics: Vortices, Flow (Dynamics), Computational fluid dynamics, Water, Reactor vessels, Sodium fast reactors, Coolants, Design, Design methodology, Evaluation methods
Proceedings Papers

Application of Vorticity Method in Auxiliary Impeller Optimization of HTR-PM Main Helium Fan

Mo Fei, Zhang Youjie
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A051, July 22–26, 2018
Paper No: ICONE26-82559
DOI: https://doi.org/10.1115/ICONE26-82559
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Topics: Helium, Impellers, Optimization, Vorticity, Flow (Dynamics), Design, Engines, Heat, Motors, Axial flow
Proceedings Papers

Study on Advanced PWR NPP Safety Related Equipment Qualification Function Requirement Design Methodology

Xu Zhao, Miao Zhuang, Yi Ke
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A003, July 22–26, 2018
Paper No: ICONE26-81212
DOI: https://doi.org/10.1115/ICONE26-81212
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Topics: Design methodology, Equipment qualification, Nuclear power stations, Pressurized water reactors, Safety, Design, China, Instrumentation, Intellectual property, Reliability
Proceedings Papers

Study on NPP Reactivity Accident Operating Strategy Design Based on Function Analysis and Task Analysis Technology

Yu Aimin, Xu Zhao, Du Yu, Sun Qian
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A005, July 22–26, 2018
Paper No: ICONE26-81478
DOI: https://doi.org/10.1115/ICONE26-81478
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Topics: Accidents, Design, Nuclear power stations, Task analysis, Defense industry, Design methodology
Proceedings Papers

Conceptual Formation of Advanced HIS Design Method for Digital I&C + HMIT

Hidekazu Yoshikawa, Zhanguo Ma, Amjad Nawaz, Ming Yang
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A017, July 2–6, 2017
Paper No: ICONE25-66530
DOI: https://doi.org/10.1115/ICONE25-66530
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Topics: Accidents, Computer simulation, Coolants, Defense industry, Design, Design methodology, Nuclear power stations, Nuclear reactor accidents, Pressurized water reactors, Risk monitoring
Proceedings Papers

Analysis on Radioactive Gas Movement and Delay Status Before Release

Bo Nan Zhu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 2–6, 2017
Paper No: ICONE25-66713
DOI: https://doi.org/10.1115/ICONE25-66713
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Topics: Delays, Activated carbon, Design, Dimensions, Flow (Dynamics), Computational methods, Design methodology, Isotopes, Nuclear fission, Nuclear power stations
Proceedings Papers

Radiation Shielding Analysis of a Spent Fuel Dry Storage Cask for FA300 Spent Fuel Assemblies

Mengqi Wang, Nan Pan, Hui Li, Baojun Jia
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A010, July 2–6, 2017
Paper No: ICONE25-66462
DOI: https://doi.org/10.1115/ICONE25-66462
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Topics: Radiation (Physics), Spent nuclear fuels, Storage, Ventilation, Concretes, Cavities, Cooling, Design, Design methodology, Fuels
Proceedings Papers

Study on the Design Methodology of Swirl Nozzle for Nuclear Reactor Pressurizer

Xiong Cao, Zhiwei Ding
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A040, July 2–6, 2017
Paper No: ICONE25-66351
DOI: https://doi.org/10.1115/ICONE25-66351
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Topics: Design methodology, Nozzles, Nuclear reactors, Sprays, Design, Nuclear reactor coolants, Flow (Dynamics), Pressure, Pressure drop, Computational fluid dynamics
Proceedings Papers

Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications

Xiawa Wang, Walker Chan, Veronika Stelmakh, Peter Fisher
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A008, July 2–6, 2017
Paper No: ICONE25-66607
DOI: https://doi.org/10.1115/ICONE25-66607
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Topics: Design, Generators, Radioisotopes, Energy conversion, Heat, Heat sinks, Insulation, Circuits, Crystals, Design methodology
Proceedings Papers

Research and Engineering Application of Repaired Fuel Assembly Reusing Technique

Lihua Wang, Qingxiang Yang, Ping Yang, Jiazheng Liu, Libing Zhu, Bo Yang, Hong Cao, Zhe Wang, Yang Ding, Jie Ding
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A024, July 2–6, 2017
Paper No: ICONE25-66659
DOI: https://doi.org/10.1115/ICONE25-66659
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Topics: Fuels, Manufacturing, Design, Fuel rods, Nuclear power stations, Economics , Rods, Safety, Computer software, Coolants
Proceedings Papers

3D Linear Bifurcation Analysis of Steel Containment Vessel

Jay Schmidt, Bernd Laskewitz
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A018, June 26–30, 2016
Paper No: ICONE24-60673
DOI: https://doi.org/10.1115/ICONE24-60673
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Topics: Bifurcation, Containment vessels, Steel, Shells, Stability, Buckling, Containment, Stress, ASME Boiler and Pressure Vessel Code, ASME Standards
Proceedings Papers

Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward

Tai Asayama, Shigeru Takaya
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, V002T08A007, June 26–30, 2016
Paper No: ICONE24-60936
DOI: https://doi.org/10.1115/ICONE24-60936
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Topics: Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, In-service inspection, Buckling, Design methodology, Engineering standards, Inspection, Stress
Proceedings Papers

Chinese Innovative Patent Technologies for the Reactor Pressure Vessel

Qian Shi, Tianqi Zhang, Xiang Fang, Wei Peng
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A008, July 7–11, 2014
Paper No: ICONE22-30694
DOI: https://doi.org/10.1115/ICONE22-30694
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Topics: Patents, Reactor vessels, Nuclear power, China, Design, Safety, Containers, Design methodology, Economics , Innovation
Proceedings Papers

Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels

Yoshihisa Ikusawa, Takayuki Ozawa, Shun Hirooka, Koji Maeda, Masato Kato, Seiichiro Maeda
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A001, July 7–11, 2014
Paper No: ICONE22-30005
DOI: https://doi.org/10.1115/ICONE22-30005
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Topics: Fuels, Irradiation (Radiation exposure), Temperature, Computers, Design methodology, Fast neutron reactors, Melting, Pressure, Thermal conductivity, Thermal properties
Proceedings Papers

The Feasibility Study of New Design Method for Combined Support of Pipes in Nuclear Engineering

Lang Han, Minjing Tang, Weifeng Jiang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A017, July 29–August 2, 2013
Paper No: ICONE21-15326
DOI: https://doi.org/10.1115/ICONE21-15326
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Topics: Design methodology, Nuclear engineering, Pipes, Plasma desorption mass spectrometry, Design, Manufacturing, Nuclear power stations, Plant design, Steelwork, Workflow
Proceedings Papers

Using a Hybrid FPGA-CPU Platform for a User-Friendly Environment in Control Systems Design: A Possible Application to Nuclear Plants

Mauro Cappelli, Stefano Di Gennaro, Fabrizio Memmi, Massimo Sepielli
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, V005T13A027, July 29–August 2, 2013
Paper No: ICONE21-16378
DOI: https://doi.org/10.1115/ICONE21-16378
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Topics: Control systems, Design, Nuclear power stations, Hardware, Simulation, Testing, Architecture, Computation, Design methodology, Engineering prototypes