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Proceedings Papers

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Qian Ma, Zhitong Yu, Peiwei Sun, Yuwen Jia, Shifa Wu

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A043, August 4–6, 2021

Paper No: ICONE28-64459

DOI: https://doi.org/10.1115/ICONE28-64459

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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models

Proceedings Papers

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

Zhitao Xu, Hongchun Wu, Youqi Zheng, Mingtao He

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A081, July 22–26, 2018

Paper No: ICONE26-82380

DOI: https://doi.org/10.1115/ICONE26-82380

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Topics: Fast neutron reactors, Geometry, Storage, China, Computers, Elastic scattering, Mean free path, Neutrons, Resonance, Simulation

Proceedings Papers

Linear Active Disturbance Rejection Control for Fast Nuclear Reactor

Liu Feng-ming, Shen Cong, Zhang Hua-xia, Zhou Shi-liang, Liu Yu-yan, Li Yu-rong, Wang Xiaoruo, Mohanned Khalid

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, V001T04A024, July 2–6, 2017

Paper No: ICONE25-66768

DOI: https://doi.org/10.1115/ICONE25-66768

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Topics: Nuclear reactors, Control equipment, Neutrons, Control systems, Dynamics (Mechanics), Fast neutron reactors, Robustness, Simulation results, State estimation, Thermal hydraulics

Proceedings Papers

Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN

Goro Soejima, Hiroki Iwai, Yasuyuki Nakamura, Hirokazu Hayashi, Haruhiko Kadowaki, Hiroyuki Mizui, Kazuya Sano

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A019, July 2–6, 2017

Paper No: ICONE25-66950

DOI: https://doi.org/10.1115/ICONE25-66950

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Topics: Contamination, Technology development, Laser cutting, Cutting, Nuclear decommissioning, Water, Pipes, Zirconium alloys, Aluminum, Boiling

Proceedings Papers

Tritium Decontamination of Contaminated System With Tritiated Heavy Water by Drying Treatment

Haruhiko Kadowaki, Akira Matsushima, Yoshiaki Nakajima

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, V004T11A007, June 26–30, 2016

Paper No: ICONE24-60531

DOI: https://doi.org/10.1115/ICONE24-60531

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Topics: Decontamination, Drying, Water, Helium, Vacuum, Dehumidifiers, Water treatment, Boiling, Circuits, Contamination

Proceedings Papers

Application of Hybrid Subgroup Decomposition Method to Gas Cooled Thermal Reactor Problem

Saam Yasseri, Farzad Rahnema

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, V004T11A005, July 7–11, 2014

Paper No: ICONE22-30353

DOI: https://doi.org/10.1115/ICONE22-30353

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Topics: Eigenvalues, Thermal reactors

Proceedings Papers

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

Zhenhua Zhang, Mingjun Chen, Peide Zhou, Qing Li, Zhiliang Meng, Guowei Zhang

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, V001T02A046, July 29–August 2, 2013

Paper No: ICONE21-16727

DOI: https://doi.org/10.1115/ICONE21-16727

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Topics: Nuclear fuel cycle, Nuclear power, Uranium, Certainty, China, Climate, Recycling, Sustainable development, Thermal reactors

Proceedings Papers

Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor

Lei He, Hongchun Wu, Liangzhi Cao, Qingjie Liu, Zhiyan Liu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 197-204, May 17–21, 2010

Paper No: ICONE18-29563

DOI: https://doi.org/10.1115/ICONE18-29563

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Topics: Absorption, Nuclides, Radioactive wastes, Resonance, Thermal reactors, Weight (Mass)

Proceedings Papers

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

Guang Jun Chen, Yu Lin Cui, Guo Guo Zhang, Hong Jun Yao

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 465-468, May 17–21, 2010

Paper No: ICONE18-29632

DOI: https://doi.org/10.1115/ICONE18-29632

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Topics: Innovation, Nuclear fuel cycle, Spent nuclear fuels, Nuclear fission, Separation (Technology), Uranium, Nuclear power stations, China, Combustion, Cycles

Proceedings Papers

Warranty Test for a High-Pressure Turbine Retrofit Using Process Data Reconciliation in Accordance With VDI 2048

Magnus Langenstein, Steffen Riehm, Jan Hansen-Schmidt

Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 361-364, May 11–15, 2008

Paper No: ICONE16-48940

DOI: https://doi.org/10.1115/ICONE16-48940

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Topics: High pressure (Physics), Turbines, Instrumentation, Nuclear power stations, Thermal reactors

Proceedings Papers

Glovebox Dismantling Activities and Decommissioning Plan for Plutonium Fuel Fabricating Facility

Akihiro Kitamura, Takashi Okada, Sinichiro Asazuma, Shinichi Uematsu, Takashi Ishibashi

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 715-720, April 25–29, 2004

Paper No: ICONE12-49511

DOI: https://doi.org/10.1115/ICONE12-49511

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Topics: Fuels, Nuclear decommissioning, Decontamination, Cycles, Databases, Industrial research, Nuclear power stations, Regulations, Ships, Storage

Proceedings Papers

Finding Megawatts in Nuclear Power Plants With Process Data Reconciliation

Magnus Langenstein, Josef Jansky, Bernd Laipple, Horst Eitschberger, Eberhard Grauf, Hermann Schalk

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 43-52, April 25–29, 2004

Paper No: ICONE12-49152

DOI: https://doi.org/10.1115/ICONE12-49152

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Topics: Nuclear power stations, Feedwater, Thermal reactors, Flow (Dynamics), Instrumentation, Boiling water reactors, Calibration, Electricity (Physics), Errors, Maintenance

Proceedings Papers

Preparatory Activities of the Fugen Decommissioning

Yukihiro Iguchi, Tsuyoshi Tajiri, Shikou Kiyota

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 671-680, April 25–29, 2004

Paper No: ICONE12-49069

DOI: https://doi.org/10.1115/ICONE12-49069

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Topics: Nuclear decommissioning, Water, Concretes, Computer-aided design, Decontamination, Density, Neutron flux, Nuclear power, Nuclides, Pressure

Proceedings Papers

Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048

Magnus Langenstein

Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 7-14, July 17–20, 2006

Paper No: ICONE14-89025

DOI: https://doi.org/10.1115/ICONE14-89025

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Topics: Boilers, Boiling water reactors, Calibration, Certainty, Design, Emergencies, Errors, Heat, Instrumentation, Nuclear power stations

NARROW

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

Linear Active Disturbance Rejection Control for Fast Nuclear Reactor

Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN

Tritium Decontamination of Contaminated System With Tritiated Heavy Water by Drying Treatment

Application of Hybrid Subgroup Decomposition Method to Gas Cooled Thermal Reactor Problem

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

Multi-Group Library Generation for the Study of Nuclide Transmutation in High Flux Engineering Test Reactor

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

Warranty Test for a High-Pressure Turbine Retrofit Using Process Data Reconciliation in Accordance With VDI 2048

Glovebox Dismantling Activities and Decommissioning Plan for Plutonium Fuel Fabricating Facility

Finding Megawatts in Nuclear Power Plants With Process Data Reconciliation

Preparatory Activities of the Fugen Decommissioning

Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048

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