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Proceedings Papers

Thermal Analysis and Structural Design of the Main Steam Containment Penetration for Multi-Modular High-Temperature Gas-Cooled Reactor Power Plant

Chaoyi Zhu, Yiyang Zhang, Huijie Yan, Jiyang Fu, Mei Huang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130135
https://doi.org/10.1115/ICONE31-130135
View Paper titled, Thermal Analysis and Structural Design of the Main Steam Containment Penetration for Multi-Modular High-Temperature Gas-Cooled Reactor Power Plant
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Topics: Containment, Heat transfer, Power stations, Steam, Structural design, Thermal analysis, Very high temperature reactors
Proceedings Papers

Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency

Salvatore Angelo Cancemi, Michela Angelucci, Rosa Lo Frano, Sandro Paci
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A070, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135798
https://doi.org/10.1115/ICONE31-135798
View Paper titled, Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency
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Topics: Metamodeling, Nuclear fuels, Artificial neural networks, Cladding systems (Building), Simulation, Temperature, Algorithms, Safety, Computer simulation, Design
Proceedings Papers

Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities

Daisuke Doi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91847
https://doi.org/10.1115/ICONE29-91847
View Paper titled, Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities
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Topics: Heating, Hydrogen, Sodium, Sodium fast reactors, Thermal analysis
Proceedings Papers

Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

Si Junping, Liu Xiaosong, Zhao Wenbin, Xu Yuheng, Lei Jin, Zhang Wenlong, Huang Gang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90468
https://doi.org/10.1115/ICONE29-90468
View Paper titled, Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method
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Topics: Fuels, Heat, High temperature, Irradiation (Radiation exposure), Manufacturing, Optimization, Steady state, Thermal analysis, Water
Proceedings Papers

High Power Electron Beam Dump at DALS

Kai Tao, Liming Huang, Yadong Ding, Zhenhai Zou, Dejun E
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91515
https://doi.org/10.1115/ICONE29-91515
View Paper titled, High Power Electron Beam Dump at DALS
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Topics: Cathode ray oscilloscopes, Design, Electron beams, Cooling, Radiation (Physics), Water, Aluminum alloys, Fins, Gamma rays, Geometry
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis

Shin Kikuchi, Hidemasa Yamano, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16075
https://doi.org/10.1115/ICONE2020-16075
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis
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Topics: Accidents, Boron, Melting, Sodium fast reactors, Steel, Thermal analysis
Proceedings Papers

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16100
https://doi.org/10.1115/ICONE2020-16100
View Paper titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs
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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors
Proceedings Papers

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A018, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16281
https://doi.org/10.1115/ICONE2020-16281
View Paper titled, Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR
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Topics: Boilers, Circuits, Computer software, Construction, Design, Fluids, Heat, Heat transfer, Heat transfer coefficients, Light water reactors
Proceedings Papers

Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A030, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16592
https://doi.org/10.1115/ICONE2020-16592
View Paper titled, Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor
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Topics: Fuels, Irradiation (Radiation exposure), Safety, Cycles, Plates (structures), Transients (Dynamics), Heat, Aluminum, Finite element analysis, Thermal analysis
Proceedings Papers

Measuring Effects of Radiation on Precipitates in Aluminum 7075-T6 Using Differential Scanning Calorimetry

Rachel C. Connick, Charles A. Hirst, Penghui Cao, Kangpyo So, R. Scott Kemp, Michael P. Short
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A090, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82457
https://doi.org/10.1115/ICONE26-82457
View Paper titled, Measuring Effects of Radiation on Precipitates in Aluminum 7075-T6 Using Differential Scanning Calorimetry
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Topics: Aluminum, Differential scanning calorimetry, Radiation effects, Irradiation (Radiation exposure), Damage, Thermal analysis, Alpha particles, Aluminum alloys, Bridges (Structures), Helium
Proceedings Papers

CFD Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A095, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82550
https://doi.org/10.1115/ICONE26-82550
View Paper titled, CFD Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Computational fluid dynamics, Pressure, Thermal analysis, Stress, Thermal insulation, Vacuum, Vessels, Design, Fatigue, Fusion reactors
Proceedings Papers

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Shanfang Huang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, Kan Wang
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81042
https://doi.org/10.1115/ICONE26-81042
View Paper titled, Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”
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Topics: Computer simulation, Education, Nuclear engineering, Nuclear reactors, Thermal analysis, Nuclear power, China, Computer software, Computers, Experimental design
Proceedings Papers

Evaluation of Heat Removal During the Failure of the Core Cooling for New Critical Assembly

Yuta Eguchi, Takanori Sugawara, Kenji Nishihara, Yujiro Tazawa, Kazufumi Tsujimoto
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82012
https://doi.org/10.1115/ICONE26-82012
View Paper titled, Evaluation of Heat Removal During the Failure of the Core Cooling for New Critical Assembly
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Topics: Cooling, Failure, Heat, Manufacturing, Design, Temperature, Cooling systems, Heat transfer coefficients, Fuels, Heat transfer
Proceedings Papers

Thermal Analysis Safety Margins Using ABAQUS for the MP-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes, Douglas S. Crawford, Gregory K. Housley
Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T04A003, June 24–28, 2018
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2018-7600
https://doi.org/10.1115/NUCLRF2018-7600
View Paper titled, Thermal Analysis Safety Margins Using ABAQUS for the MP-2 Experiment in the Advanced Test Reactor
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Topics: Safety, Thermal analysis, Fuels, Irradiation (Radiation exposure), Water, Aluminum, Finite element analysis, Plates (structures), Coolants, Finite element model
Proceedings Papers

Critical Thermal Safety Technologies of Spent Fuel Dry Storage Cask

Qiong-Hui Tang, Xiao-Ying Qi, Chu-Yang Yu, Xue-Ling Zhang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A045, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66621
https://doi.org/10.1115/ICONE25-66621
View Paper titled, Critical Thermal Safety Technologies of Spent Fuel Dry Storage Cask
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Topics: Safety, Spent nuclear fuels, Storage, Thermal analysis, Computational fluid dynamics, Design, Heat, Optimization, Radiation (Physics), Simulation
Proceedings Papers

Design and Optimization of Temperature Acquisition System for Determination of Effective Thermal Conductivity of Pebble Bed

Pengxin Cheng, Cheng Ren, Yongyong Wu, Rui Li
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66148
https://doi.org/10.1115/ICONE25-66148
View Paper titled, Design and Optimization of Temperature Acquisition System for Determination of Effective Thermal Conductivity of Pebble Bed
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Topics: Design, Optimization, Temperature, Thermal conductivity, Data acquisition systems, Heat transfer, Computer software, Errors, Hardware, Measurement systems
Proceedings Papers

Thermal Analysis of the FSP-1 Experiment in the Advanced Test Reactor

Grant L. Hawkes, Nicolas E. Woolstenhulme
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A059, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60752
https://doi.org/10.1115/ICONE24-60752
View Paper titled, Thermal Analysis of the FSP-1 Experiment in the Advanced Test Reactor
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Topics: Thermal analysis, Safety, Fuels, Plates (structures), Coolants, Uranium, Alloys, Aluminum, Canals, Cooling
Proceedings Papers

Heat Transfer Simulation of the Fuel Transport Cask for Spherical Fuel Elements in Molten Salt Reactor

Yang Liu, Jun Wang
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A047, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60633
https://doi.org/10.1115/ICONE24-60633
View Paper titled, Heat Transfer Simulation of the Fuel Transport Cask for Spherical Fuel Elements in Molten Salt Reactor
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Topics: Fuels, Heat transfer, Molten salt reactors, Simulation, Accidents, Boiling water reactors, Design, Operating temperature, Pressurized water reactors, Radiation (Physics)
Proceedings Papers

Single-Channel Thermal Analysis of Fully Ceramic Microencapsulated Fuel via Two-Temperature Homogenized Model

Yoonhee Lee, Nam Zin Cho, Sun Kyo Chung
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30072
https://doi.org/10.1115/ICONE22-30072
View Paper titled, Single-Channel Thermal Analysis of Fully Ceramic Microencapsulated Fuel via Two-Temperature Homogenized Model
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Topics: Ceramics, Fuels, Temperature, Thermal analysis, Particulate matter, Very high temperature reactors, Accidents, Dimensions, Finite element methods, Finite element model
Proceedings Papers

Modelling of RBMK Spent Nuclear Fuel Characteristics

Arturas Smaizys, Povilas Poskas, Ernestas Narkunas
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, V004T08A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31005
https://doi.org/10.1115/ICONE22-31005
View Paper titled, Modelling of RBMK Spent Nuclear Fuel Characteristics
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Topics: Modeling, Spent nuclear fuels, Fuels, Radioisotopes, Evaluation methods, Heat, Neutron sources, Nuclear fission, Nuclear power stations, Safety