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Proceedings Papers

Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis

Kiminobu Hojo, David Rudland
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136517
https://doi.org/10.1115/ICONE31-136517
View Paper titled, Comparison of K-Solutions of Rectangular Flaw With Semi-Elliptical Flaw for PWSCC Growth Analysis
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Topics: ASME Standards, Coolants, Fracture (Materials), Japan Society of Mechanical Engineers, JSME Standards, Metals, Pipes, Shapes, Stress corrosion cracking, Surges
Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
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Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
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

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Richard Hernandez, Nicholas R. Brown, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A041, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16758
https://doi.org/10.1115/ICONE2020-16758
View Paper titled, RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT
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Topics: Boron, Critical heat flux, Pool boiling, Testing, Coolants, Design, Shapes, Accidents, Heat flux, Heat transfer
Proceedings Papers

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Ji Soo Ahn, Michael Bluck, Matthew Eaton, Chris Jackson
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A006, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81424
https://doi.org/10.1115/ICONE26-81424
View Paper titled, A Validation of RELAP on Predicting Nuclear Power Plant Phenomena
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Topics: Nuclear power stations, Thermal stratification, Pipes, Surges, Computational fluid dynamics, Cooling, Errors, Feedwater, Junctions, Piping systems
Proceedings Papers

Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support

Jianrong Zou, Shaochong Zhou
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A069, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66875
https://doi.org/10.1115/ICONE25-66875
View Paper titled, Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support
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Topics: ASME Standards, Boilers, Computational methods, Design, Engineering design, Finite element methods, Flange connections, Flanges, Girders, Junctions
Proceedings Papers

Thermal Stratification Analysis and Fatigue Evaluation for Pressurizer Surge Line in Nuclear Power Plant

Xiao Xu, Pan Liu, Guihe Zhang, Dasheng Wang, Ting Jin
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A082, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67118
https://doi.org/10.1115/ICONE25-67118
View Paper titled, Thermal Stratification Analysis and Fatigue Evaluation for Pressurizer Surge Line in Nuclear Power Plant
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Topics: Fatigue, Nuclear power stations, Surges, Thermal stratification, Stress, Dimensions, Boundary layers, Fluids, Numerical analysis, Temperature
Proceedings Papers

Analysis of CAP1400 Reactor Coolant Hot Leg Flow Field

Niu Tingting, Liu Chunli, Xia Shuan
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67038
https://doi.org/10.1115/ICONE25-67038
View Paper titled, Analysis of CAP1400 Reactor Coolant Hot Leg Flow Field
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Topics: Flow (Dynamics), Nuclear reactor coolants, Pipes, Instrumentation, Coolants, Boilers, Computational fluid dynamics, Computer software, Nozzles, Pumps
Proceedings Papers

Experimental Investigation on the Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67251
https://doi.org/10.1115/ICONE25-67251
View Paper titled, Experimental Investigation on the Pipe Leakage
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Topics: Leakage, Pipes, Temperature, Fracture (Materials), Pipelines, Nuclear power stations, High temperature, Fatigue, Fluids, High pressure (Physics)
Proceedings Papers

Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project

Huadong Zhu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66339
https://doi.org/10.1115/ICONE25-66339
View Paper titled, Boring Analysis in Solving Out-of-Tolerance of Wall Thickness of Surge Line in Nuclear Power Project
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Topics: Nuclear power, Surges, Wall thickness, Design, Pipes, Nuclear reactor coolants, Pressure, Engineering drawings, Fittings, Heating
Proceedings Papers

Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line

Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A063, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66893
https://doi.org/10.1115/ICONE25-66893
View Paper titled, Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line
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Topics: Flow (Dynamics), Friction, Steam, Surges, Water, Pressure drop, Pressure, Accidents, Coolants, Manufacturing
Proceedings Papers

Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line

Y. L. Shen, Tao Lu, Bo Liu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67026
https://doi.org/10.1115/ICONE25-67026
View Paper titled, Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line
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Topics: Computer simulation, Surges, Thermal stratification, Temperature, Computational fluid dynamics, Fluids, Pipes, Temperature distribution, Degrees of freedom, Fatigue
Proceedings Papers

Fragility of a Flood Defense Structure Subjected to Multi-Hazard Scenario

Saran Srikanth Bodda, Harleen Kaur Sandhu, Abhinav Gupta
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A015, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60508
https://doi.org/10.1115/ICONE24-60508
View Paper titled, Fragility of a Flood Defense Structure Subjected to Multi-Hazard Scenario
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Topics: Defense industry, Floods, Hazards, Concretes, Dams, Gravity (Force), Nuclear power stations, Failure, Dam failures, Deformation
Proceedings Papers

Investigation of Bypass Valve Positions on Performance of Closed Brayton Cycle

Xiao Li, Xiaoyong Yang, Youjie Zhang
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60152
https://doi.org/10.1115/ICONE24-60152
View Paper titled, Investigation of Bypass Valve Positions on Performance of Closed Brayton Cycle
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Topics: Brayton cycle, Valves, Algebra, Compression, Compressors, Computer simulation, Design, Heat, Integrated systems, Metals
Proceedings Papers

Influence of Passive Safety Systems on a Cladding Temperature Condition of Fuel Rod Simulators

Oleg I. Melikhov, Ilya V. Elkin, Vladimir I. Melikhov, Sergey M. Nikonov, Sergey S. Pylev, Sergey I. Zaitsev, Maxim O. Zakutaev, Dmitry I. Dorofeev
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A037, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30296
https://doi.org/10.1115/ICONE22-30296
View Paper titled, Influence of Passive Safety Systems on a Cladding Temperature Condition of Fuel Rod Simulators
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Topics: Cladding systems (Building), Fuel rods, Safety, Temperature, Pipelines, Rupture, Accidents, Fuels, Leakage, Modeling
Proceedings Papers

Long Term SBO With Selected Mitigative Measures: MELCOR Parametric Calculations for a 2-Loop PWR

Adolf Rydl, Bernd Jaeckel, Jonathan C. Birchley, Terttaliisa Lind
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A012, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30351
https://doi.org/10.1115/ICONE22-30351
View Paper titled, Long Term SBO With Selected Mitigative Measures: MELCOR Parametric Calculations for a 2-Loop PWR
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Topics: Pressurized water reactors, Containment, Failure, Ablation (Vaporization technology), Accidents, Concretes, Surges, Water, Accident management, Boilers
Proceedings Papers

The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification

Jianjun Wang, Zengfang Ge, Zhongning Sun, Changqi Yan
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, V004T10A029, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30686
https://doi.org/10.1115/ICONE22-30686
View Paper titled, The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification
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Topics: Stress analysis (Engineering), Surges, Thermal stratification, Stress, Transients (Dynamics), Heat, Temperature, Pressurized water reactors, Computational fluid dynamics, Design
Proceedings Papers

Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor

Xu Yang, Tao Zhou, Daping Lin, Xiaolu Fang, Baixu Chen, Xiaolong Ru
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, V004T10A005, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30187
https://doi.org/10.1115/ICONE22-30187
View Paper titled, Numerical Simulation of Steam Generator Tube Rupture Sequence in ADS Reactor
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Topics: Boilers, Computer simulation, Rupture, Steam, Coolants, Flow (Dynamics), Particulate matter, Accidents, Corrosion, Safety
Proceedings Papers

Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution

Yang Yang, Hong Xia, Xian Zeng, Dali Yu
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30470
https://doi.org/10.1115/ICONE22-30470
View Paper titled, Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution
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Topics: Numerical analysis, Stress concentration, Surges, Parallel strand lumber, Stress, Finite element methods, Steady state, Finite volume methods, Temperature, Temperature distribution
Proceedings Papers

Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR

Shasha Yin, Liang Gao, Wenxi Tian, Yapei Zhang, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A046, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31066
https://doi.org/10.1115/ICONE22-31066
View Paper titled, Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR
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Topics: Accidents, Flow (Dynamics), Safety, Coolants, Transients (Dynamics), Heat, Steady state, Boilers, Feedwater, Pressurized water reactors