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Proceedings Papers

Simulated Temperature Profiles for Corrosion Products Deposited in ITER Experimental Loop

Muhammad Arslan, Ma Yan, Muhammad Ali Shahzad, Lei Jinyun, Shahroze Ahmed
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A021, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66695
https://doi.org/10.1115/ICONE25-66695
View Paper titled, Simulated Temperature Profiles for Corrosion Products Deposited in ITER Experimental Loop
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Topics: Corrosion, Temperature profiles, Temperature, Coolants, Temperature distribution, Particulate matter, Pressure, Thermocouples
Proceedings Papers

Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor

Jian Ruan, Yang Zou, Minghai Li, Hongjie Xu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A009, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66228
https://doi.org/10.1115/ICONE25-66228
View Paper titled, Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor
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Topics: High temperature, Coolants, Temperature, Flow (Dynamics), Stress, Control equipment, Temperature control, Transient analysis, Transients (Dynamics), Air flow
Proceedings Papers

Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code

Alessio Pesetti, Mariano Tarantino, Piero Gaggini, Giuseppe Polazzi, Nicola Forgione
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A039, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67419
https://doi.org/10.1115/ICONE25-67419
View Paper titled, Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code
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Topics: Boilers, Control equipment, Control systems, Data acquisition, Disks, Eutectic alloys, Flow (Dynamics), Heat exchangers, Hot water heating, Hydraulic lifts
Proceedings Papers

Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium

Deyang Cui, Xiangzhou Cai, Jingen Chen, Chenggang Yu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67177
https://doi.org/10.1115/ICONE25-67177
View Paper titled, Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium
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Topics: Fuels, Molten salt reactors, Sustainability, Uranium, Nuclear fuel cycle, Light water reactors, Breeder reactors, Energy generation, Energy sustainability, Industrial research
Proceedings Papers

Toward an Open-Source Neutronics Code for Circulating-Fuel Reactors

Julien de Troullioud de Lanversin, Alexander Glaser, Malte Göttsche
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66584
https://doi.org/10.1115/ICONE25-66584
View Paper titled, Toward an Open-Source Neutronics Code for Circulating-Fuel Reactors
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Topics: Fuels, Molten salt reactors, Algorithms, Computer simulation, Particulate matter, Resolution (Optics), Simulation
Proceedings Papers

Void Reactivity Effect Research on Liquid Metal Cooled Fast Reactor

Yang Lyu, Xiao Liang
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A037, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67368
https://doi.org/10.1115/ICONE25-67368
View Paper titled, Void Reactivity Effect Research on Liquid Metal Cooled Fast Reactor
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Topics: Fast neutron reactors, Liquid metals, Bubbles, Computational methods, Coolants, Design, Fuels, Industrial research, Liquid metal cooled reactors, Nuclear industry
Proceedings Papers

Comparison and Analysis on Two Kinds of Passive Residual Heat Removal System Designs Under Station Blackout Accident for Integral Small Modular Reactor

Fei Li, Feng Shen, Ning Bai, Zhaocan Meng
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A007, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66181
https://doi.org/10.1115/ICONE25-66181
View Paper titled, Comparison and Analysis on Two Kinds of Passive Residual Heat Removal System Designs Under Station Blackout Accident for Integral Small Modular Reactor
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Topics: Accidents, Heat, Small modular reactors, Design, Coolants, Hydraulic drive systems, Safety, Simulation models
Proceedings Papers

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core

Minoru Goto, Shohei Ueta, Jun Aihara, Yoshitomo Inaba, Yuji Fukaya, Yukio Tachibana, Koji Okamoto
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A031, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67110
https://doi.org/10.1115/ICONE25-67110
View Paper titled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core
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Topics: Design, Fuels, Safety, Security, Very high temperature reactors, Pressure, Oxygen, Coating processes, Coatings, Failure
Proceedings Papers

Development of Manufacturing Technologies for the ITER Toroidal Field Coil: Insertion Processes of Conductors

K. Yamamoto, T. Matsumoto, T. Baba, A. Yamamoto, S. Kanbayashi, T. Kagawa, T. Okamoto, S. Fujii, S. Ando, K. Matsui, M. Nakahira, N. Koizumi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A055, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67986
https://doi.org/10.1115/ICONE25-67986
View Paper titled, Development of Manufacturing Technologies for the ITER Toroidal Field Coil: Insertion Processes of Conductors
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Topics: Deformation, Dimensions, Errors, Fiber lasers, Forging, Gas tungsten arc welding, Heat treating (Metalworking), Laser welding, Machining, Manufacturing
Proceedings Papers

Development of the Severe Accident Evaluation Method on Second Coolant Leakages From the PHTS in a Loop-Type Sodium-Cooled Fast Reactor

Fumiaki Yamada, Yuya Imaizumi, Masahiro Nishimura, Yoshitaka Fukano, Mitsuhiro Arikawa
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67581
https://doi.org/10.1115/ICONE25-67581
View Paper titled, Development of the Severe Accident Evaluation Method on Second Coolant Leakages From the PHTS in a Loop-Type Sodium-Cooled Fast Reactor
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Topics: Accidents, Coolants, Evaluation methods, Leakage, Sodium fast reactors, Sodium, Countermeasures, Heat, Reactor vessels, Transients (Dynamics)
Proceedings Papers

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

Masaaki Nakano, Kazutaka Ohashi, Koji Okamoto
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66907
https://doi.org/10.1115/ICONE25-66907
View Paper titled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents
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Topics: Accidents, Fuels, Safety, Security, Very high temperature reactors, Design, Scram, Uranium, Accident management, Combustion
Proceedings Papers

A Simulation of Small Break Loss of Coolant Accident (SB-LOCA) in AP1000 Nuclear Power Plant Using RELAP5-MV

Eltayeb Yousif, Zhang Zhijian, Tian Zhao-fei, A. M. Mustafa
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A043, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67469
https://doi.org/10.1115/ICONE25-67469
View Paper titled, A Simulation of Small Break Loss of Coolant Accident (SB-LOCA) in AP1000 Nuclear Power Plant Using RELAP5-MV
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Topics: Accidents, Coolants, Nuclear power stations, Simulation, Computer software, Modeling, Nuclear power, Thermal hydraulics, Transients (Dynamics), Computer programming
Proceedings Papers

CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

Hironori Nakamura, Kazuhiro Oyama, Satoshi Hayakawa, Tomoaki Ogata, Seiichiro Maeda, Takayuki Ozawa
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A013, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66307
https://doi.org/10.1115/ICONE25-66307
View Paper titled, CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan
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Topics: Computational fluid dynamics, Fuel rods, Wire, Fuels, Boundary-value problems, Cladding systems (Building), Geometry, Simulation, Sodium fast reactors, Temperature
Proceedings Papers

Comparative Study of Basic Reactor Physics of the DFR Concept Using U-Pu and TRU Fuel Salts

Xiang Wang, Rafael Macian-Juan
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66035
https://doi.org/10.1115/ICONE25-66035
View Paper titled, Comparative Study of Basic Reactor Physics of the DFR Concept Using U-Pu and TRU Fuel Salts
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Topics: Fuels, Physics, Molten salt reactors, Fast neutron reactors, Fluids, Liquid metals, Neutrons, Sodium fast reactors, Steady state, Temperature
Proceedings Papers

Reinforcement of Emergency Power Supply System for Next Generation SFR

Nobuyuki Ishikawa, Yoshitaka Chikazawa, Daisuke Sato, Risako Ikari
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A038, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67369
https://doi.org/10.1115/ICONE25-67369
View Paper titled, Reinforcement of Emergency Power Supply System for Next Generation SFR
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Topics: Emergency power, Sodium fast reactors, Design, Generators, Cooling systems, Emergencies, Optimization, Accidents, Diesel generators, Fuels
Proceedings Papers

Thermal Hydraulics Analysis of the Fluoride-Salt-Cooled, High-Temperature Reactor

Yao Fu, Qiang Sun, Chong Zhou, Yang Zou
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A020, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66588
https://doi.org/10.1115/ICONE25-66588
View Paper titled, Thermal Hydraulics Analysis of the Fluoride-Salt-Cooled, High-Temperature Reactor
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Topics: High temperature, Thermal hydraulics, Transients (Dynamics), Coolants, Design, Flow (Dynamics), Heat, Accidents, China, Fuels
Proceedings Papers

Breeding Properties Study on High Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66961
https://doi.org/10.1115/ICONE25-66961
View Paper titled, Breeding Properties Study on High Power Thorium Molten Salt Reactor
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Topics: Molten salt reactors, Breeder reactors, Fluids, Fuels, Generation IV reactors, Security, Temperature, Transients (Dynamics)
Proceedings Papers

Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-NBI

Chundong Hu, Mingshan Wu, Yahong Xie, Jianglong Wei, Ling Yu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A032, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67125
https://doi.org/10.1115/ICONE25-67125
View Paper titled, Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-NBI
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Topics: Electrons, Silencers, Emissions, Ions, Plasmas (Ionized gases), Safety, Diamonds, Electron emission, Geometry, Heat
Proceedings Papers

The R&D Activities and Future Plan of 4MW Hot Cathode Ion Source for EAST Neutral Beam Injector

Yahong Xie, Chundong Hu, Sheng Liu, Jun Li, Yuanlai Xie, Lizhen Liang, Caichao Jiang, Jianglong Wei, Yongjian Xu, Ling Tao, Yuming Gu, Shiyong Chen, Peng Sheng, Zhimin Liu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66218
https://doi.org/10.1115/ICONE25-66218
View Paper titled, The R&D Activities and Future Plan of 4MW Hot Cathode Ion Source for EAST Neutral Beam Injector
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Topics: Ejectors, Neutral beams, Plasmas (Ionized gases), Steady state, Tokamaks, Diamonds, Electrons, Feedback, Heating, Hydrogen
Proceedings Papers

Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs

Feng Gou, Fubing Chen, Yujie Dong
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A044, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67492
https://doi.org/10.1115/ICONE25-67492
View Paper titled, Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs
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Topics: Systems analysis, Accidents, China, Design, High temperature, Power stations, Regulations, Safety, Thermal hydraulics