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Proceedings Papers

Current Status and Development of Core Calculation Methodology for Sodium Cooled Fast Reactor in Mitsubishi

Kazumi Ikeda, Hiroyuki Moriwaki, Wataru Nakazato
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 145-154, May 17–21, 2010
Paper No: ICONE18-29755
DOI: https://doi.org/10.1115/ICONE18-29755
View Paper titled, Current Status and Development of Core Calculation Methodology for Sodium Cooled Fast Reactor in Mitsubishi
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Topics: Sodium fast reactors, Design, Nuclear power
Proceedings Papers

Analysis for Inverse Flow in Moderator Channels of Supercritical Water Cooled Reactor

Shengwei Fu, Zhihong Xu, Yanhua Yang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 219-225, May 17–21, 2010
Paper No: ICONE18-29844
DOI: https://doi.org/10.1115/ICONE18-29844
View Paper titled, Analysis for Inverse Flow in Moderator Channels of Supercritical Water Cooled Reactor
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Topics: Flow (Dynamics), Supercritical water reactors, Water
Proceedings Papers

Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System

Hiroyuki Sato, Hirofumi Ohashi, Yujiro Tazawa, Nariaki Sakaba, Yukio Tachibana
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 1-10, May 17–21, 2010
Paper No: ICONE18-29108
DOI: https://doi.org/10.1115/ICONE18-29108
View Paper titled, Safety Evaluation of the HTTR-IS Nuclear Hydrogen Production System
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Topics: Hydrogen production, Safety, Evaluation methods, Pressure, Temperature, Acceptance criteria, Accidents, Cooling systems, Design, Fuels
Proceedings Papers

Optimization Design for a New Cascade of Helium Compressor With Enhanced Pressure Ratio

Yanli Long, Limin Xu, Jinglei Yu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 289-295, May 17–21, 2010
Paper No: ICONE18-30023
DOI: https://doi.org/10.1115/ICONE18-30023
View Paper titled, Optimization Design for a New Cascade of Helium Compressor With Enhanced Pressure Ratio
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Topics: Cascades (Fluid dynamics), Compressors, Design, Helium, Optimization, Pressure, Very high temperature reactors, Artificial neural networks, Turbines, Air compressors
Proceedings Papers

Design and Analysis of Testing Platform for Study of Graphite Dust Emission Behavior During Accident Conditions

Zhipeng Chen, Suyuan Yu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 349-354, May 17–21, 2010
Paper No: ICONE18-30312
DOI: https://doi.org/10.1115/ICONE18-30312
View Paper titled, Design and Analysis of Testing Platform for Study of Graphite Dust Emission Behavior During Accident Conditions
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Topics: Accidents, Design, Dust, Emissions, Graphite, Testing, Very high temperature reactors, Circuits, Nuclear fission, Coolants
Proceedings Papers

Thermal-Hydraulic Modeling of CANDU-SCWR and Linear Dynamic Model Development

Peiwei Sun, Jin Jiang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 155-163, May 17–21, 2010
Paper No: ICONE18-29780
DOI: https://doi.org/10.1115/ICONE18-29780
View Paper titled, Thermal-Hydraulic Modeling of CANDU-SCWR and Linear Dynamic Model Development
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Topics: Dynamic models, Modeling, Supercritical water reactors, Design, Control systems, Dynamic analysis, Generation IV reactors, Simulation, Steady state
Proceedings Papers

Safety Analyses of the Lead-Bismuth Eutectic Cooled Accelerator Driven System XT-ADS

Xue-Nong Chen, Danilo D’Andrea, Claudia Matzerath Boccaccini, Werner Maschek
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 103-114, May 17–21, 2010
Paper No: ICONE18-29658
DOI: https://doi.org/10.1115/ICONE18-29658
View Paper titled, Safety Analyses of the Lead-Bismuth Eutectic Cooled Accelerator Driven System XT-ADS
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Topics: Safety, Flow (Dynamics), Computer simulation, Coolants, Transients (Dynamics), Accidents, Design, Integral equations, Natural convection, Oscillations
Proceedings Papers

Analysis of Radioactive Source Term for Modular HTGR During Normal Operation

Jianzhu Cao, Tao Liu, Yuanyu Wu, Hong Li, Yuanzhong Liu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 297-302, May 17–21, 2010
Paper No: ICONE18-30075
DOI: https://doi.org/10.1115/ICONE18-30075
View Paper titled, Analysis of Radioactive Source Term for Modular HTGR During Normal Operation
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Topics: Very high temperature reactors, China, Circuits, Nuclear fission, Design, Gas cooled reactors, High temperature, Nuclides
Proceedings Papers

Advances in Pressure Tube Reactor Technology

W. C. H. Kupferschmidt, R. B. Duffey, L. Leung, R. Didsbury
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 227-232, May 17–21, 2010
Paper No: ICONE18-29878
DOI: https://doi.org/10.1115/ICONE18-29878
View Paper titled, Advances in Pressure Tube Reactor Technology
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Topics: Pressure, Construction, Industrial research, Innovation, Security, Sustainability, Water
Proceedings Papers

Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor

Shoji Takada, Kenji Abe, Yoshiyuki Inagaki
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 53-58, May 17–21, 2010
Paper No: ICONE18-29379
DOI: https://doi.org/10.1115/ICONE18-29379
View Paper titled, Conceptual Structure Design of High Temperature Isolation Valve for High Temperature Gas Cooled Reactor
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Topics: Design, Gas cooled reactors, High temperature, Valves, Stress, Temperature, Accidents, Creep, Helium, Hydrogen production
Proceedings Papers

Coefficients for I-131 Sorption on Different Surfaces

M. M. Stempniewicz
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 35-42, May 17–21, 2010
Paper No: ICONE18-29290
DOI: https://doi.org/10.1115/ICONE18-29290
View Paper titled, Coefficients for I-131 Sorption on Different Surfaces
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Topics: Sorption, Computers, Spectra (Spectroscopy), Dust, Equilibrium (Physics), Graphite, Nuclear fission, Safety, Steel, Desorption
Proceedings Papers

Construction of Westinghouse AP1000™ Nuclear Power Plants in China

Grenville Harrop, Bill P. Poirier
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 303-309, May 17–21, 2010
Paper No: ICONE18-30077
DOI: https://doi.org/10.1115/ICONE18-30077
View Paper titled, Construction of Westinghouse AP1000™ Nuclear Power Plants in China
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Topics: China, Construction, Nuclear power stations, Containment vessels, Design, Concretes, Manufacturing, Pressurized water reactors, Boilers, Canals
Proceedings Papers

Materials Research in Support of SCWR Development: Current Areas, Gaps and Needs

Wenyue Zheng, Dave Guzonas, D. Brady, W. Cook, J. Luo
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 233-239, May 17–21, 2010
Paper No: ICONE18-29899
DOI: https://doi.org/10.1115/ICONE18-29899
View Paper titled, Materials Research in Support of SCWR Development: Current Areas, Gaps and Needs
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Topics: Materials research, Supercritical water reactors, Corrosion, Water, Alloys, Collaboration, Creep, Damage, Fusion reactors, Hydropower
Proceedings Papers

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

Shohei Ueta, Jun Aihara, Masaki Honda, Noboru Furihata, Kazuhiro Sawa
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 11-12, May 17–21, 2010
Paper No: ICONE18-29206
DOI: https://doi.org/10.1115/ICONE18-29206
View Paper titled, Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup
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Topics: Fuels, Very high temperature reactors, Carbon, Coating processes, Coatings, Particulate matter, Nuclear fission, High temperature, Nuclear power, Polishing equipment
Proceedings Papers

The Constructability Analysis of AP1000 Containment Vessel Bottom Head

Nianci Gao, Xiaopeng Fang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 165-170, May 17–21, 2010
Paper No: ICONE18-29783
DOI: https://doi.org/10.1115/ICONE18-29783
View Paper titled, The Constructability Analysis of AP1000 Containment Vessel Bottom Head
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Topics: Containment vessels
Proceedings Papers

Mission and Status of the First Two Next Generation Nuclear Plant Fuel Irradiation Experiments in the Advanced Test Reactor

S. Blaine Grover, David A. Petti, John T. Maki
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 311-320, May 17–21, 2010
Paper No: ICONE18-30139
DOI: https://doi.org/10.1115/ICONE18-30139
View Paper titled, Mission and Status of the First Two Next Generation Nuclear Plant Fuel Irradiation Experiments in the Advanced Test Reactor
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Topics: Fuels, Irradiation (Radiation exposure), Nuclear power stations, Nuclear fission, Design, Particulate matter, Testing, High temperature, Monitoring systems, Nuclear power
Proceedings Papers

Gas Flow Simulations in Randomly Distributed Pebbles

Xiang Zhao, Trent Montgomery, Sijun Zhang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 171-179, May 17–21, 2010
Paper No: ICONE18-29785
DOI: https://doi.org/10.1115/ICONE18-29785
View Paper titled, Gas Flow Simulations in Randomly Distributed Pebbles
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Topics: Computational fluid dynamics, Engineering simulation, Gas flow, Geometry, Large eddy simulation, Modeling, Reynolds-averaged Navier–Stokes equations, Simulation, Turbulence, Flow (Dynamics)
Proceedings Papers

Simulation of a Steam Generator Tube Rupture Accident in a Lead-Cooled Accelerator Driven System

Michael Flad, Shisheng Wang, Werner Maschek
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 241-249, May 17–21, 2010
Paper No: ICONE18-29910
DOI: https://doi.org/10.1115/ICONE18-29910
View Paper titled, Simulation of a Steam Generator Tube Rupture Accident in a Lead-Cooled Accelerator Driven System
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Topics: Accidents, Boilers, Rupture, Simulation, Water, Design, Safety, Computer simulation, Coolants, Damage
Proceedings Papers

Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results

Yoshihiko Sakamoto, Shoji Kotake, Kazumi Aoto, Mikio Toda
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 355-363, May 17–21, 2010
Paper No: ICONE18-30322
DOI: https://doi.org/10.1115/ICONE18-30322
View Paper titled, Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results
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Topics: Design, Fast neutron reactors, Nuclear reactors, Reactor vessels, Circuits, Cooling, Cycles, Damage, Optimization, Piping design
Proceedings Papers

Experimental Research of Pebble Dynamics of Two-Region Reactor Core in HTR

Xiuzhi Zhang, Youjie Zhang, Xingtuan Yang, Zhiyong Liu, Shengyao Jiang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 115-118, May 17–21, 2010
Paper No: ICONE18-29660
DOI: https://doi.org/10.1115/ICONE18-29660
View Paper titled, Experimental Research of Pebble Dynamics of Two-Region Reactor Core in HTR
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Topics: Dynamics (Mechanics), Dimensions