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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

Paper No: ICONE29-91847

DOI: https://doi.org/10.1115/ICONE29-91847

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Topics: Heating, Hydrogen, Sodium, Sodium fast reactors, Thermal analysis

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

Paper No: ICONE29-91515

DOI: https://doi.org/10.1115/ICONE29-91515

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Topics: Cathode ray oscilloscopes, Design, Electron beams, Cooling, Radiation (Physics), Water, Aluminum alloys, Fins, Gamma rays, Geometry

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

Paper No: ICONE29-90468

DOI: https://doi.org/10.1115/ICONE29-90468

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Topics: Fuels, Heat, High temperature, Irradiation (Radiation exposure), Manufacturing, Optimization, Steady state, Thermal analysis, Water

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

Paper No: ICONE2020-16075

DOI: https://doi.org/10.1115/ICONE2020-16075

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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

Paper No: ICONE2020-16100

DOI: https://doi.org/10.1115/ICONE2020-16100

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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

Paper No: ICONE2020-16281

DOI: https://doi.org/10.1115/ICONE2020-16281

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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

Paper No: ICONE2020-16592

DOI: https://doi.org/10.1115/ICONE2020-16592

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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

Paper No: ICONE26-82457

DOI: https://doi.org/10.1115/ICONE26-82457

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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

Paper No: ICONE26-82550

DOI: https://doi.org/10.1115/ICONE26-82550

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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

Paper No: ICONE26-81042

DOI: https://doi.org/10.1115/ICONE26-81042

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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

Paper No: ICONE26-82012

DOI: https://doi.org/10.1115/ICONE26-82012

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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

Paper No: NUCLRF2018-7600

DOI: https://doi.org/10.1115/NUCLRF2018-7600

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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

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

Paper No: ICONE25-66148

DOI: https://doi.org/10.1115/ICONE25-66148

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Topics: Design, Optimization, Temperature, Thermal conductivity, Data acquisition systems, Heat transfer, Computer software, Errors, Hardware, Measurement systems

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

Paper No: ICONE25-66621

DOI: https://doi.org/10.1115/ICONE25-66621

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Topics: Safety, Spent nuclear fuels, Storage, Thermal analysis, Computational fluid dynamics, Design, Heat, Optimization, Radiation (Physics), Simulation

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

Paper No: ICONE24-60752

DOI: https://doi.org/10.1115/ICONE24-60752

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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

Paper No: ICONE24-60633

DOI: https://doi.org/10.1115/ICONE24-60633

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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

Paper No: ICONE22-30072

DOI: https://doi.org/10.1115/ICONE22-30072

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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

Paper No: ICONE22-31005

DOI: https://doi.org/10.1115/ICONE22-31005

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Topics: Modeling, Spent nuclear fuels, Fuels, Radioisotopes, Evaluation methods, Heat, Neutron sources, Nuclear fission, Nuclear power stations, Safety

Proceedings Papers

Characteristic Analysis of Supercritical Water-Cooled Reactor During Uncontrolled CR Withdrawal at Normal Operation Transient

Wanxu Cheng, Tao Zhou, Liang Liu, Mingqiang Song, Bangyang Xia

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A023, July 29–August 2, 2013

Paper No: ICONE21-15774

DOI: https://doi.org/10.1115/ICONE21-15774

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Topics: Cladding systems (Building), Temperature, Transients (Dynamics), Water, Feedback, Coolants, Density, Flow (Dynamics), Pressure, Steam

Proceedings Papers

Out-of-Pile Heat Transfer Test Device for Low Pressure Irradiation Capsule

Yongzhe Ma, Peisheng Zhang

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, V001T02A025, July 29–August 2, 2013

Paper No: ICONE21-15822

DOI: https://doi.org/10.1115/ICONE21-15822

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Topics: Heat transfer, Irradiation (Radiation exposure), Pressure, China, Design, Temperature, Thermal analysis, Convection, Fast neutron reactors, Fuels

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NARROW

Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities

High Power Electron Beam Dump at DALS

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

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

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

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

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

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

CFD Thermal Analysis of ITER Pressure Suppression Tanks

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

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

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

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

Critical Thermal Safety Technologies of Spent Fuel Dry Storage Cask

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

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

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

Modelling of RBMK Spent Nuclear Fuel Characteristics

Characteristic Analysis of Supercritical Water-Cooled Reactor During Uncontrolled CR Withdrawal at Normal Operation Transient

Out-of-Pile Heat Transfer Test Device for Low Pressure Irradiation Capsule

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