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Proceedings Papers

Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap

Donghao Li, Daogang Lu, Yuxuan Zhu, Yu Liu
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92137
https://doi.org/10.1115/ICONE29-92137
View Paper titled, Study on the Added Mass of the Double-Fixed Constrained Flexible Coaxial Cylindrical Shells With Liquid in the Narrow Gap
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Topics: Fluid structure interaction, Pipes, Shells, Vibration, Finite element model, Fluids, Water, Computer software, Fast neutron reactors, Heat shielding
Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92274
https://doi.org/10.1115/ICONE29-92274
View Paper titled, Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap
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Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)
Proceedings Papers

The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant

Zilong Wang, Deyi Liu, Ming Zhao, Li Wang, Jie Xu
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T13A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64423
https://doi.org/10.1115/ICONE28-64423
View Paper titled, The Safety Analysis of the Design of the Reactor Coolant Pump Heat Shield in Qinshan Nuclear Power Plant
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Topics: Design, Heat shielding, Nuclear power stations, Nuclear reactor coolants, Pumps, Safety
Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16465
https://doi.org/10.1115/ICONE2020-16465
View Paper titled, Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure
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Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design
Proceedings Papers

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

Kun Xu, Minyou Ye, Yuntao Song, Mingzhun Lei, Shifeng Mao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67291
https://doi.org/10.1115/ICONE25-67291
View Paper titled, Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket
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Topics: Ceramics, Helium, Lithium, Design, China, Energy generation, Tokamaks, Vacuum, Vessels, Bridges (Structures)
Proceedings Papers

On Experimental Simulation of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding

Alexander N. Gershuni, Alexander P. Nishchik, Evgeviy N. Pis’mennyi, Victor G. Razumovskiy, Igor L. Pioro
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A038, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61159
https://doi.org/10.1115/ICONE24-61159
View Paper titled, On Experimental Simulation of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding
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Topics: Condensation, Evaporation, Heat shielding, Simulation, Heat, Cooling, Heat pipes, Reliability, Safety, Vapors
Proceedings Papers

Design of the Spent Fuel Storage Well of HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A003, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60051
https://doi.org/10.1115/ICONE24-60051
View Paper titled, Design of the Spent Fuel Storage Well of HTR-PM
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Topics: Design, Spent fuel storage, Spent nuclear fuels, Storage, Fuels, Safety, Wells, Heat, Accidents, High temperature
Proceedings Papers

On Features of Thermal Design of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding

A. N. Gershuni, A. P. Nishchik, E. N. Pis'mennyi, V. G. Razumovskiy, I. L. Pioro
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A004, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30133
https://doi.org/10.1115/ICONE22-30133
View Paper titled, On Features of Thermal Design of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding
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Topics: Condensation, Design, Evaporation, Heat shielding, Cavities, Heat, Safety, Containment, Emergencies, Nuclear engineering
Proceedings Papers

Primary Shielding Design for an Optimized Molten Salt Reactor

Zhihong Zhang, Xiaobin Xia, Jianhua Wang, Changyuan Li
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, V001T04A020, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15821
https://doi.org/10.1115/ICONE21-15821
View Paper titled, Primary Shielding Design for an Optimized Molten Salt Reactor
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Topics: Design, Molten salt reactors, Heat shielding, Neutrons, Heat, Carbon steel, Concrete walls, Containment, Fuels, Generation IV reactors