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Proceedings Papers

Design and Development of DeRisk: A Fault Tree Analysis Program Package

Zhenxu Zhou, Hao Nie, Qin Zhang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81291
https://doi.org/10.1115/ICONE26-81291
View Paper titled, Design and Development of DeRisk: A Fault Tree Analysis Program Package
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Topics: Design, Fourier transform spectroscopy, Graphical user interfaces, Reliability, Algorithms, Computer software, Cycles, Dynamics (Mechanics), Engineers, Military systems
Proceedings Papers

Design of a Platform for Safety Justification of Safety-Critical Software

Guo Jia, Yang Ming
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, V001T04A043, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67548
https://doi.org/10.1115/ICONE25-67548
View Paper titled, Design of a Platform for Safety Justification of Safety-Critical Software
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Topics: Computer software, Design, Safety, Reliability, Computer-aided engineering, Accidents, Cycles, Drag (Fluid dynamics), Graphical user interfaces, Nuclear power stations
Proceedings Papers

Research on Emergency System of Injection Estimation of Reactor Core Recovery and Reactor Core Decay Heat Removal

Liao Feiye, Jiang Pingting, Liu Wang, He Dongyu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A003, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66110
https://doi.org/10.1115/ICONE25-66110
View Paper titled, Research on Emergency System of Injection Estimation of Reactor Core Recovery and Reactor Core Decay Heat Removal
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Topics: Emergencies, Heat, Accidents, Nuclear power stations, Errors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Graphical user interfaces, Matlab, Public utilities
Proceedings Papers

GRAPE: Graphical RELAP/SCDAPSIM Analysis Platform for Education and Engineering

Masahiro Tatsumi, Kosuke Tsujita, Kotaro Sato, Yohei Tamari
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, V004T12A003, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60562
https://doi.org/10.1115/ICONE24-60562
View Paper titled, GRAPE: Graphical RELAP/SCDAPSIM Analysis Platform for Education and Engineering
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Topics: Education, Visualization, Accidents, Boiling water reactors, Graphical user interfaces, Maintainability, Nuclear engineering, Pressurized water reactors, Safety, Sensitivity analysis
Proceedings Papers

Graphical User Interface With Reverse-Engineering of the Cyclic Voltammetry Method for Electrochemical Processes of Used Nuclear Fuel

Samaneh Rakhshan Pouri, Supathorn Phongikaroon
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A026, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60439
https://doi.org/10.1115/ICONE24-60439
View Paper titled, Graphical User Interface With Reverse-Engineering of the Cyclic Voltammetry Method for Electrochemical Processes of Used Nuclear Fuel
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Topics: Graphical user interfaces, Nuclear fuels, Reverse engineering, Uranium, Computer software, Design, Diffusion (Physics), Errors, Matlab, Robustness
Proceedings Papers

Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors

Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Yunzhao Li
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A058, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30950
https://doi.org/10.1115/ICONE22-30950
View Paper titled, Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors
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Topics: Fuel management, Geometry, Graphical user interfaces, Isotopes, Manufacturing, Modeling, Rods
Proceedings Papers

A New Data-Driven ATHLET – ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits

Georgios Theodoridis, Angel Papukchiev, Dominik Scholz, Georg Lerchl
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, V004T10A047, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31119
https://doi.org/10.1115/ICONE22-31119
View Paper titled, A New Data-Driven ATHLET – ANSYS CFD Coupling Method for Efficient Simulation of Nuclear Power Plant Circuits
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Topics: Circuits, Computational fluid dynamics, Nuclear power stations, Simulation, Junctions, Graphical user interfaces, Heat transfer, Two-phase flow
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16378
https://doi.org/10.1115/ICONE21-16378
View Paper titled, Using a Hybrid FPGA-CPU Platform for a User-Friendly Environment in Control Systems Design: A Possible Application to Nuclear Plants
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Topics: Control systems, Design, Nuclear power stations, Hardware, Simulation, Testing, Architecture, Computation, Design methodology, Engineering prototypes
Proceedings Papers

Application of RELSIM-RELAP/SCDAPSIM for University Training and Simulator Development

Chris M. Allison, Brian S. Allison, Uwe Luettringhaus, Judith K. Hohorst
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 425-430, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30215
https://doi.org/10.1115/ICONE18-30215
View Paper titled, Application of RELSIM-RELAP/SCDAPSIM for University Training and Simulator Development
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Topics: Accidents, Blocks (Building materials), Engineering education, Fuels, Graphical user interfaces, Hydraulic drive systems, Nuclear reactors, Pipes, Risk management, Simulation
Proceedings Papers

Network Computing Infrastructure to Share Tools and Data in GNEP

Guehee Kim, Yoshio Suzuki, Naoya Teshima
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 463-470, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75304
https://doi.org/10.1115/ICONE17-75304
View Paper titled, Network Computing Infrastructure to Share Tools and Data in GNEP
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Topics: Collaboration, Design, Encryption, Engineering prototypes, Gates (Closures), Graphical user interfaces, Leakage, Nuclear power, Security
Proceedings Papers

Building an Application-Specific Grid Computing Environment Using ITBL for Nuclear Material Engineering

Yuichi Tsujita, Tatsumi Arima, Kazuya Idemitsu, Yoshio Suzuki, Hideo Kimura
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 55-63, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48223
https://doi.org/10.1115/ICONE16-48223
View Paper titled, Building an Application-Specific Grid Computing Environment Using ITBL for Nuclear Material Engineering
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Topics: Materials science, Computation, Visualization, American Petroleum Institute, Computer software, Graphical user interfaces, Nuclear fuels, Simulation, Atoms, Combustion
Proceedings Papers

Visualization of Heat Transfer and Core Damage With RGUI 1.5

George L. Mesina
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 1077-1086, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22698
https://doi.org/10.1115/ICONE10-22698
View Paper titled, Visualization of Heat Transfer and Core Damage With RGUI 1.5
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Topics: Damage, Heat transfer, Visualization, Graphical user interfaces, Computer software, Accidents, Fuel rods, Heat, Modeling, Nuclear power stations
Proceedings Papers

Performance, Accuracy and Efficiency Evaluation of a Three-Dimensional Whole-Core Neutron Transport Code AGENT

Tatjana Jevremovic, Mathieu Hursin, Nader Satvat, John Hopkins, Shanjie Xiao, Godfree Gert
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 435-445, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89561
https://doi.org/10.1115/ICONE14-89561
View Paper titled, Performance, Accuracy and Efficiency Evaluation of a Three-Dimensional Whole-Core Neutron Transport Code AGENT
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Topics: Neutrons, Geometry, Design, Algebra, Computer simulation, Cross section (Physics), Diffusion (Physics), Graphical user interfaces, Leakage, Modeling