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Proceedings Papers

The Dependence of Pool Scrubbing Decontamination Factor on Particle Number Density: Modeling Based on Bubble Mass and Energy Balance

Yasuteru Sibamoto, Haomin Sun, Yoshiyasu Hirose, Yutaka Kukita
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16223
https://doi.org/10.1115/ICONE2020-16223
View Paper titled, The Dependence of Pool Scrubbing Decontamination Factor on Particle Number Density: Modeling Based on Bubble Mass and Energy Balance
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Topics: Bubbles, Condensation, Decontamination, Density, Energy budget (Physics), Modeling, Particulate matter
Proceedings Papers

Development of Five-Equation Drift Flux Model for Thermal Non-Equilibrium Phenomena in LWRs

Shanbin Shi, Xiaoqin Zhang, Xiaodong Sun, Hongbin Zhang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A118, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67981
https://doi.org/10.1115/ICONE25-67981
View Paper titled, Development of Five-Equation Drift Flux Model for Thermal Non-Equilibrium Phenomena in LWRs
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Topics: Equilibrium (Physics), Light water reactors, Constitutive equations, Energy budget (Physics), Thermal equilibrium, Eigenvalues, Energy transformation, Finite difference methods, Finite element methods, Kinematics
Proceedings Papers

Technology of Protection Against the Dynamic Effect of Nuclear Pipe Rupture

Feng He, Feng Yuan, Honglei Ai, Xinjun Wang, Xifeng Lu, Yongbo Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A042, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66381
https://doi.org/10.1115/ICONE25-66381
View Paper titled, Technology of Protection Against the Dynamic Effect of Nuclear Pipe Rupture
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Topics: Pipes, Rupture, Energy budget (Physics), Finite element analysis, Deformation, Thrust, Damage, Energy dissipation, Finite element model, Hinges
Proceedings Papers

Process Design of Heat Pump Evaporation Technology for Liquid Radioactive Waste Treatment

Jia Lu, Yan Zhou
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66989
https://doi.org/10.1115/ICONE25-66989
View Paper titled, Process Design of Heat Pump Evaporation Technology for Liquid Radioactive Waste Treatment
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Topics: Evaporation, Heat pumps, Process design, Radioactive wastes, Compressors, Design, Electrolytes, Energy budget (Physics), Energy efficiency, Separation (Technology)
Proceedings Papers

Use of Algebraic Heat Flux Models to Improve Heat Transfer Predictions for Supercritical Pressure Fluids

Vera Papp, Andrea Pucciarelli, Medhat Sharabi, Walter Ambrosini
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, V004T10A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60298
https://doi.org/10.1115/ICONE24-60298
View Paper titled, Use of Algebraic Heat Flux Models to Improve Heat Transfer Predictions for Supercritical Pressure Fluids
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Topics: Algebra, Fluids, Heat flux, Heat transfer, Pressure, Temperature, Turbulence, Energy budget (Physics), Engineering simulation, Flow (Dynamics)
Proceedings Papers

The Influence of the Wall Stored Energy on the Natural-Circulation Mode in the Core Make-Up Tank Test Facility

Mingzhang Zhu, Huajian Chang, Han Wang, Xi Xu, Yang Shi
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60414
https://doi.org/10.1115/ICONE24-60414
View Paper titled, The Influence of the Wall Stored Energy on the Natural-Circulation Mode in the Core Make-Up Tank Test Facility
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Topics: Test facilities, Flow (Dynamics), Simulation, Thermal stratification, Engineering prototypes, Water, Density, Design, Energy budget (Physics), Heat
Proceedings Papers

Global Balance of Plant in NPPs Using Process Data Reconciliation According to VDI 2048

Magnus Langenstein, Bernd Laipple
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, V001T01A027, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31277
https://doi.org/10.1115/ICONE22-31277
View Paper titled, Global Balance of Plant in NPPs Using Process Data Reconciliation According to VDI 2048
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Topics: Nuclear power stations, Feedwater, Flow (Dynamics), Monitoring systems, Boilers, Energy budget (Physics), Gases, Heat transfer coefficients, Leakage, Maintenance
Proceedings Papers

Analysis of Dynamic Effects Associated With Postulated Breaks of Piping

Manqing Qin, Xinghua Li, Jicheng Zhao
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, V001T01A016, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15273
https://doi.org/10.1115/ICONE21-15273
View Paper titled, Analysis of Dynamic Effects Associated With Postulated Breaks of Piping
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Topics: Pipes, Stress, Computer simulation, Defense industry, Energy budget (Physics), Hydrodynamics, Leak-before-break, Nuclear design, Piping systems, Regulations
Proceedings Papers

Modeling of the SNL S-CO 2 Loop With ANL Plant Dynamics Code

Anton Moisseytsev, James J. Sienicki
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 641-650, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54548
https://doi.org/10.1115/ICONE20-POWER2012-54548
View Paper titled, Modeling of the SNL S-CO 2 Loop With ANL Plant Dynamics Code
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Topics: Dynamics (Mechanics), Modeling, Supercritical carbon dioxide, Brayton cycle, Steady state, Compressors, Energy budget (Physics), Heat losses, Power converters, Turbines
Proceedings Papers

Nuclear Power Plant Simulator for Concept Design and Performance Analysis

B. N. M. Mills, R. I. Latchford, V. Badalassi
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 121-128, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54475
https://doi.org/10.1115/ICONE20-POWER2012-54475
View Paper titled, Nuclear Power Plant Simulator for Concept Design and Performance Analysis
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Topics: Design, Nuclear power stations, Nuclear reactors, Boilers, Matlab, Simulation, Small modular reactors, Turbines, Aerospace industry, Computer software
Proceedings Papers

Analysis of Operator Responses to Mitigate Temperature Rise in Electrical Auxiliary Building

M. James Hardy, Matthew F. King, Ryan Bigelow
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 865-871, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30119
https://doi.org/10.1115/ICONE18-30119
View Paper titled, Analysis of Operator Responses to Mitigate Temperature Rise in Electrical Auxiliary Building
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Topics: Temperature, Computational fluid dynamics, Heat, Air conditioning, Damage, Energy budget (Physics), HVAC equipment, Probabilistic risk assessment, Probability, Simulation
Proceedings Papers

Bubble Sliding Process on Subcooling Flow Boiling in Vertical Rectangular Narrow Channel

De-wen Yuan, Liang-ming Pan, Jing-hua Wei, De-qi Chen
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 1037-1047, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30086
https://doi.org/10.1115/ICONE18-30086
View Paper titled, Bubble Sliding Process on Subcooling Flow Boiling in Vertical Rectangular Narrow Channel
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Topics: Boiling, Bubbles, Flow (Dynamics), Subcooling, Heat transfer, Energy budget (Physics), Evaporation, Fluids, Forced convection, Heat flux
Proceedings Papers

Analysis of Coupled Neutronic-Thermohydraulic Instabilities in Supercritical Water-Cooled Reactor by Lumped Parameter Modeling

Manmohan Pandey, M. Ashok Kumar
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 357-366, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48407
https://doi.org/10.1115/ICONE16-48407
View Paper titled, Analysis of Coupled Neutronic-Thermohydraulic Instabilities in Supercritical Water-Cooled Reactor by Lumped Parameter Modeling
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Topics: Modeling, Water, Coolants, Engineering simulation, Simulation, Stability, Bifurcation, Dynamics (Mechanics), Limit cycles, Neutrons
Proceedings Papers

Conceptual Analysis of the Thermo-Hydraulic Characteristics of Fission Electric Cell Reactors

C. Morrow, G. Rochau, J. Cash, D. King
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 133-140, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22539
https://doi.org/10.1115/ICONE10-22539
View Paper titled, Conceptual Analysis of the Thermo-Hydraulic Characteristics of Fission Electric Cell Reactors
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Topics: Nuclear fission, Energy conversion, Heat transfer, Design, Temperature, Economics , Emissions, Energy budget (Physics), Heat, Nuclear energy research
Proceedings Papers

Heat and Fission Product Transport in a Molten U-Zr-O Pool With Crust

J. I. Yun, K. Y. Suh, C. S. Kang
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 723-728, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22438
https://doi.org/10.1115/ICONE10-22438
View Paper titled, Heat and Fission Product Transport in a Molten U-Zr-O Pool With Crust
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Topics: Heat, Nuclear fission, Zirconium, Accidents, Geometry, Alpha decay, Bubbles, Chemical properties, Dynamics (Mechanics), Energy budget (Physics)
Proceedings Papers

Single Rod Heat Transfer Tests to Study the Effects of Crud Deposition

G. Wang, W. A. Byers, Z. E. Karoutas, L. E. Hochreiter, M. Y. Young, R. J. Jacko
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 275-282, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89261
https://doi.org/10.1115/ICONE14-89261
View Paper titled, Single Rod Heat Transfer Tests to Study the Effects of Crud Deposition
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Topics: Boiling, Heat transfer, Pressurized water reactors, Forced convection, Fuels, Test facilities, Thermocouples, Water, Boron, Coolants
Proceedings Papers

Experimental Study on Contact Angle of Water Droplet in High-Temperature Condition

Yoshinori Hirose, Tsukasa Hayashi, Tatsuya Hazuku, Tomoji Takamasa
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 709-716, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89614
https://doi.org/10.1115/ICONE14-89614
View Paper titled, Experimental Study on Contact Angle of Water Droplet in High-Temperature Condition
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Topics: Drops, High temperature, Water, Boiling water reactors, Aluminum, Energy budget (Physics), Gases, Heat transfer, Nitrogen, Pressure vessels