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Proceedings Papers

Nuclear Power Hazard and Economic Risk Assessment

T. Margulies

Proc. ASME. IMECE97, Safety Engineering and Risk Analysis, 1-9, November 16–21, 1997

Paper No: IMECE1997-0028

DOI: https://doi.org/10.1115/IMECE1997-0028

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Topics: Accidents, Contamination, Density, Emergency preparedness, Filtration, Financial risk, Hazards, Instrumentation, Light water reactors, Nuclear power

Proceedings Papers

Investigation of the Real Process Data on Basis of Closed Mass- and Energy Balances in Nuclear Power Plants (NPPs)

E. Grauf, J. Jansky, M. Langenstein

Proc. ASME. IMECE99, Safety Engineering and Risk Analysis, 23-40, November 14–19, 1999

Paper No: IMECE1999-1148

DOI: https://doi.org/10.1115/IMECE1999-1148

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Topics: Nuclear power stations, Chain, Maintenance, Redundancy (Engineering), Calibration, Computer software, Coolants, Light water reactors, Manufacturing engineering, Temperature

Proceedings Papers

Motion Analysis of Robot Arm for Obstacle Avoidance

Celeste Colberg Poley, Balakumar Balachandran

Proc. ASME. IMECE2017, Volume 4A: Dynamics, Vibration, and Control, V04AT05A013, November 3–9, 2017

Paper No: IMECE2017-71010

DOI: https://doi.org/10.1115/IMECE2017-71010

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Topics: Robots, Algorithms, Surgery, Path planning, Degrees of freedom, End effectors, Robotics, Bone, Construction, Engineering simulation

Proceedings Papers

Motion Analysis of Robot Arm With Movement Restriction

Celeste Colberg Poley, Balakumar Balachandran

Proc. ASME. IMECE2016, Volume 4A: Dynamics, Vibration, and Control, V04AT05A007, November 11–17, 2016

Paper No: IMECE2016-65513

DOI: https://doi.org/10.1115/IMECE2016-65513

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Topics: Robots, Surgery, Manipulators, Algorithms, End effectors, Engineering simulation, Light water reactors, Path planning, Robotics, Simulation

Proceedings Papers

Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO 2 -BeO Fuel Behavior

Rong Liu, Wenzhong Zhou

Proc. ASME. IMECE2015, Volume 6B: Energy, V06BT07A026, November 13–19, 2015

Paper No: IMECE2015-52504

DOI: https://doi.org/10.1115/IMECE2015-52504

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Topics: Fuels, Simulation, Thermal conductivity, Cladding systems (Building), Nuclear fission, Light water reactors, Thermal stresses, Cracking (Materials), Creep, Diffusion (Physics)

Proceedings Papers

Fully Coupled Simulation of Oxygen and Heat Diffusion for (U, Pu)O 2 Fuel in Both FBR and LWR

Wenzhong Zhou, Rong Liu

Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A031, November 14–20, 2014

Paper No: IMECE2014-40212

DOI: https://doi.org/10.1115/IMECE2014-40212

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Topics: Fuels, Light water reactors, Oxygen, Simulation, Thermal diffusion, Metals, Fast neutron reactors, Temperature, Simulation results, Temperature distribution

Proceedings Papers

COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Vefa N. Kucukboyaci, Liping Cao, Yixing Sung

Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A027, November 14–20, 2014

Paper No: IMECE2014-38513

DOI: https://doi.org/10.1115/IMECE2014-38513

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Topics: Accidents, Fuels, Irradiation (Radiation exposure), Simulation, Fuel rods, Transients (Dynamics), Coolants, Physics, Safety, Boiling

Proceedings Papers

Natural Convection Heat Transfer Phenomena in Packed Bed Systems

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

Proc. ASME. IMECE2014, Volume 8B: Heat Transfer and Thermal Engineering, V08BT10A077, November 14–20, 2014

Paper No: IMECE2014-38694

DOI: https://doi.org/10.1115/IMECE2014-38694

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Topics: Heat transfer, Natural convection, Particulate matter, Fuels, Cladding systems (Building), Design, Fluids, Heat, Helium, Porous materials

Proceedings Papers

Evaluation of Advanced Thermal-Hydraulic System Codes for Safety Analysis of Integral Type PWR

J. Choi, B. Woods

Proc. ASME. IMECE2013, Volume 6B: Energy, V06BT07A046, November 15–21, 2013

Paper No: IMECE2013-63215

DOI: https://doi.org/10.1115/IMECE2013-63215

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Topics: Pressurized water reactors, Safety, Design, Boundary-value problems, Computers, Containment, Cooling, Heat conduction, Simulation, Transients (Dynamics)

Proceedings Papers

A Rapid Computational Method for Reducing the Search Space Required in Nuclear Reactor Optimization

Andrew G. Osborne, Mark R. Deinert

Proc. ASME. IMECE2010, Volume 11: New Developments in Simulation Methods and Software for Engineering Applications; Safety Engineering, Risk Analysis and Reliability Methods; Transportation Systems, 15-20, November 12–18, 2010

Paper No: IMECE2010-40244

DOI: https://doi.org/10.1115/IMECE2010-40244

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Topics: Computational methods, Nuclear reactors, Optimization, Physics, Fuels, Cycles, Design, Light water reactors, Nuclear fuels, Optimization algorithms

Proceedings Papers

Self-Excited Vibration of Cross-Shaped Tube Bundle in Cross Flow

Fumio Inada, Takashi Nishihara, Akira Yasuo, Ryo Morita, Akihiro Sakashita, Jun Mizutani

Proc. ASME. IMECE2002, 5th International Symposium on Fluid Structure Interaction, Aeroelasticity, and Flow Induced Vibration and Noise, 643-650, November 17–22, 2002

Paper No: IMECE2002-32754

DOI: https://doi.org/10.1115/IMECE2002-32754

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Topics: Cross-flow, Vibration, Reynolds number, Design, Drag (Fluid dynamics), Flow (Dynamics), Light water reactors, Water tunnels

Proceedings Papers

Turbulence-Induced Fluid Dynamic Forces Acting on Cross-Shaped Tube Bundle in Cross Flow

Takashi Nishihara, Fumio Inada, Akira Yasuo, Ryo Morita, Akihiro Sakashita, Jun Mizutani

Proc. ASME. IMECE2002, 5th International Symposium on Fluid Structure Interaction, Aeroelasticity, and Flow Induced Vibration and Noise, 651-658, November 17–22, 2002

Paper No: IMECE2002-32758

DOI: https://doi.org/10.1115/IMECE2002-32758

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Topics: Cross-flow, Fluid-dynamic forces, Turbulence, Drag (Fluid dynamics), Excitation, Fluids, Oscillations, Reynolds number, Spectral energy distribution, Vibration

Proceedings Papers

A Physical Model for Predicting Annular Film Flow Droplet Entrainment in Heat Transfer Systems

M. J. Holowach, L. E. Hochreiter, F. B. Cheung

Proc. ASME. IMECE2002, Energy Conversion, 89-101, November 17–22, 2002

Paper No: IMECE2002-39279

DOI: https://doi.org/10.1115/IMECE2002-39279

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Topics: Drops, Film flow, Heat transfer, Light water reactors, Computers, Design, Energy transformation, Flow (Dynamics), Fluid dynamics, Momentum

Proceedings Papers

A Model for Predicting Droplet Entrainment at a Quench Front in Thermal Hydraulic Analysis Codes

M. J. Holowach, L. E. Hochreiter, J. H. Mahaffy, F. B. Cheung

Proc. ASME. IMECE2003, Heat Transfer, Volume 4, 3-14, November 15–21, 2003

Paper No: IMECE2003-41126

DOI: https://doi.org/10.1115/IMECE2003-41126

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Topics: Drops, Light water reactors, Boiling, Boundary layers, Computers, Coolants, Design, Energy transformation, Fluid dynamics, Fluids

Proceedings Papers

Using Small X-Ray Beams to Understand Corrosion in Nuclear Fuel Cladding

Arthur T. Motta, Aylin Yilmazbayhan, Robert J. Comstock, Barry Lai, Zhonghou Cai

Proc. ASME. IMECE2004, X-Rays in Mechanical Engineering Applications, 103-108, November 13–19, 2004

Paper No: IMECE2004-62475

DOI: https://doi.org/10.1115/IMECE2004-62475

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Topics: Cladding systems (Building), Corrosion, Nuclear fuels, X-rays, Alloys, Circuits, Cycles, Design, Diffraction, Fluorescence

Proceedings Papers

A Large-Scale Numerical Simulation on Bubbly and Liquid Film Flows in Narrow Fuel Channels

K. Takase, H. Yoshida, Y. Ose, H. Akimoto

Proc. ASME. IMECE2005, Fluids Engineering, 947-954, November 5–11, 2005

Paper No: IMECE2005-80772

DOI: https://doi.org/10.1115/IMECE2005-80772

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Topics: Computer simulation, Flow (Dynamics), Fuels, Liquid films, Light water reactors, Two-phase flow, Water vapor, Bubbles, Bubbly flow, Design

Proceedings Papers

Thermal Stratification and Mixing in an Open Water Pool by Submerged Mixtures of Steam and Air

Timothy L. Norman, Hyun-Sik Park, Shripad T. Revankar, Mamoru Ishii, Joseph M. Kelly

Proc. ASME. IMECE2006, Energy Conversion and Resources, 137-151, November 5–10, 2006

Paper No: IMECE2006-15735

DOI: https://doi.org/10.1115/IMECE2006-15735

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Topics: Steam, Thermal stratification, Water, Condensation, Pressure, Accidents, Boiling water reactors, Containment, Coolants, Flow (Dynamics)

Proceedings Papers

A Large-Scale Simulation on Two-Phase Flow Characteristics Around Duel Rods in a Tight-Lattice Core

K. Takase, H. Yoshida, Y. Ose, H. Akimoto

Proc. ASME. IMECE2006, Energy Conversion and Resources, 159-166, November 5–10, 2006

Paper No: IMECE2006-16177

DOI: https://doi.org/10.1115/IMECE2006-16177

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Topics: Rods, Simulation, Two-phase flow, Fuel rods, Flow (Dynamics), Water, Fuels, Vapors, Bridges (Structures), Computation

NARROW

Nuclear Power Hazard and Economic Risk Assessment

Investigation of the Real Process Data on Basis of Closed Mass- and Energy Balances in Nuclear Power Plants (NPPs)

Motion Analysis of Robot Arm for Obstacle Avoidance

Motion Analysis of Robot Arm With Movement Restriction

Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO 2 -BeO Fuel Behavior

Fully Coupled Simulation of Oxygen and Heat Diffusion for (U, Pu)O 2 Fuel in Both FBR and LWR

COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Natural Convection Heat Transfer Phenomena in Packed Bed Systems

Evaluation of Advanced Thermal-Hydraulic System Codes for Safety Analysis of Integral Type PWR

A Rapid Computational Method for Reducing the Search Space Required in Nuclear Reactor Optimization

Self-Excited Vibration of Cross-Shaped Tube Bundle in Cross Flow

Turbulence-Induced Fluid Dynamic Forces Acting on Cross-Shaped Tube Bundle in Cross Flow

A Physical Model for Predicting Annular Film Flow Droplet Entrainment in Heat Transfer Systems

A Model for Predicting Droplet Entrainment at a Quench Front in Thermal Hydraulic Analysis Codes

Using Small X-Ray Beams to Understand Corrosion in Nuclear Fuel Cladding

A Large-Scale Numerical Simulation on Bubbly and Liquid Film Flows in Narrow Fuel Channels

Thermal Stratification and Mixing in an Open Water Pool by Submerged Mixtures of Steam and Air

A Large-Scale Simulation on Two-Phase Flow Characteristics Around Duel Rods in a Tight-Lattice Core

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