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Proceedings Papers

Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor

Hiroyuki Sato, Takeshi Aoki, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16050
https://doi.org/10.1115/ICONE2020-16050
View Paper titled, Guidance for Developing Fuel Design Limit of High Temperature Gas-Cooled Reactor
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Topics: Design, Fuels, Safety, Very high temperature reactors
Proceedings Papers

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Rodney Harvill, Jeff Lane, John Link, Anita Gates, Tom Kindred
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16058
https://doi.org/10.1115/ICONE2020-16058
View Paper titled, Modeling the Molten Salt Reactor Experiment With the GOTHIC Code
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Topics: Design, Modeling, Molten salt reactors, Heat, Fuels, Neutrons, Transients (Dynamics), Flow (Dynamics), Fluids, Nuclear fission
Proceedings Papers

Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)

Takeshi Aoki, Kazuyoshi Isaka, Hiroyuki Sato, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16196
https://doi.org/10.1115/ICONE2020-16196
View Paper titled, Development of a Flow Network Calculation Code (FNCC) for High Temperature Gas-Cooled Reactors (HTGRs)
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Topics: Flow (Dynamics), Very high temperature reactors
Proceedings Papers

Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor

Takeshi Aoki, Hiroyuki Sato, Hirofumi Ohashi
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16199
https://doi.org/10.1115/ICONE2020-16199
View Paper titled, Methodology Development for Transient Flow Distribution Analysis in High Temperature Gas-Cooled Reactor
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Topics: Unsteady flow, Very high temperature reactors
Proceedings Papers

HTGR Power-Level Control Only by Regulating Helium Flowrate

Zhe Dong
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16218
https://doi.org/10.1115/ICONE2020-16218
View Paper titled, HTGR Power-Level Control Only by Regulating Helium Flowrate
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Topics: Helium, Stability, Very high temperature reactors
Proceedings Papers

Walk-Away Safe Modular Small and Micro Reactors for Electricity Generation and Process Heat

Mohamed S. El-Genk, Timothy Schriener
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16238
https://doi.org/10.1115/ICONE2020-16238
View Paper titled, Walk-Away Safe Modular Small and Micro Reactors for Electricity Generation and Process Heat
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Topics: Electric power generation, Heat, Safety
Proceedings Papers

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Cai Zhiyun, Ren Yun, Lai Jianyong, Zhang Yulong, Liu Hang, Liu Xianghong, Liu Minghao, Ye Zhu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16341
https://doi.org/10.1115/ICONE2020-16341
View Paper titled, Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)
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Topics: Equilibrium (Physics), Simulation analysis, Transients (Dynamics), Flow (Dynamics), Nuclear reactor coolants, Pressure, Safety, Valves, Water, Boundary-value problems
Proceedings Papers

Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR

Jose A. Nogueron, Zhang Baorui, Zhou Zhiwei
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A008, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16345
https://doi.org/10.1115/ICONE2020-16345
View Paper titled, Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR
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Topics: Cooling, Design, Helium, Tokamaks, Computational fluid dynamics, Bridges (Structures), China, Combustion, Computer software, Cycles
Proceedings Papers

Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field

Mao Uchida, Moe Hirakawa, Aaru Sano, Keisuke Inoue, Takaaki Sakai, Toshiki Ezure, Masaaki Tanaka
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16418
https://doi.org/10.1115/ICONE2020-16418
View Paper titled, Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field
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Topics: Design, Flow (Dynamics), Sodium fast reactors, Vortices, Computational fluid dynamics, Reactor vessels, Water, Coolants, Evaluation methods, Particulate matter
Proceedings Papers

Design and Operational Challenges of Switching Working Fluid for a Gen IV Nuclear Powered Closed-Cycle Gas Turbine: Case Studies of Nitrogen and Air, Helium and Argon

Emmanuel O. Osigwe, Arnold Gad-Briggs, Nasiru Tukur, Pericles Pilidis
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A011, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16591
https://doi.org/10.1115/ICONE2020-16591
View Paper titled, Design and Operational Challenges of Switching Working Fluid for a Gen IV Nuclear Powered Closed-Cycle Gas Turbine: Case Studies of Nitrogen and Air, Helium and Argon
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Topics: Closed-cycle gas turbines, Design, Fluids, Helium, Nitrogen, Turbomachinery
Proceedings Papers

A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation

Junjie Zhou, Qin Zeng, Jinchen Yang, Yi Yang, Ying Shi, Yanyi Jiang
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A010, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16427
https://doi.org/10.1115/ICONE2020-16427
View Paper titled, A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation
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Topics: Neutron flux, Proton beams, Spallation (Nuclear physics)
Proceedings Papers

Large-Scale Rig for the Characterization of DCC at Sub-Atmospheric Pressure

R. Lo Frano, A. Pesetti, D. Aquaro, M. Olcese
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16662
https://doi.org/10.1115/ICONE2020-16662
View Paper titled, Large-Scale Rig for the Characterization of DCC at Sub-Atmospheric Pressure
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Topics: Condensation, Pressure, Safety
Proceedings Papers

Synergy of an SMR for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16671
https://doi.org/10.1115/ICONE2020-16671
View Paper titled, Synergy of an SMR for Addressing Remote Communities Non-Nuclear Waste
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Topics: Central heating, Diesel, Fossil fuels, Fuels, Heat, Heating, Plastics, Pyrolysis, Stress, Thermal energy
Proceedings Papers

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

R. Lo Frano, M. Puccini, E. Stefanelli
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16711
https://doi.org/10.1115/ICONE2020-16711
View Paper titled, Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles
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Topics: Manufacturing
Proceedings Papers

Development of Safety-Enhanced Fast Reactor by Using Minor Actinide Bearing Internal Blanket

Sho Fuchita, Satoshi Takeda, Koji Fujimura, Toshikazu Takeda, Kazuhiro Fujimata
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16746
https://doi.org/10.1115/ICONE2020-16746
View Paper titled, Development of Safety-Enhanced Fast Reactor by Using Minor Actinide Bearing Internal Blanket
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Topics: Bearings, Fast neutron reactors, Safety, Sodium, Sodium fast reactors
Proceedings Papers

Sodium Fire Analysis Using a Sodium Chemistry Package in MELCOR

Mitsuhiro Aoyagi, Akihiro Uchibori, Takahi Takata, David L. Y. Louie, Andrew J. Clark
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16751
https://doi.org/10.1115/ICONE2020-16751
View Paper titled, Sodium Fire Analysis Using a Sodium Chemistry Package in MELCOR
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Topics: Chemistry, Fire, Liquid pool fires, Sodium