Search Results | IMECE | ASME Digital Collection

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume II, 275-282, November 16–21, 1997

Paper No: IMECE1997-0121

DOI: https://doi.org/10.1115/IMECE1997-0121

View Paper

Topics: Boilers, Engineering simulation, Simulation, Wear, Vibration, Errors, Failure, Fluids, In-service inspection, Inspection

Proceedings Papers

Flow-Induced Vibration of a Tube Array in the Inlet Region of a High Performance Steam Generator: Part 1 — Turbulence Induced Vibration

Toshihiko Iwase, Takeshi Sunami, Kazuhiko Matsutani, Tomomichi Nakamura, Njuki W. Mureithi, Ayao Tsuge, Yoshinori Watanabe, Ken-ichi Tomomatsu, Osamu Takaba

Proc. ASME. IMECE97, 4th International Symposium on Fluid-Structure Interactions, Aeroelasticity, Flow-Induced Vibration and Noise: Volume II, 301-308, November 16–21, 1997

Paper No: IMECE1997-0124

DOI: https://doi.org/10.1115/IMECE1997-0124

View Paper

Topics: Boilers, Flow-induced vibrations, Turbulence, Vibration, Design, Nuclear power stations, Pressurized water reactors, Random vibration, Stability, Stress

Proceedings Papers

Simulation of Some Emergency Operating Procedure for VVER-440 Reactors

József Bánáti, György Ézsöl

Proc. ASME. IMECE97, Nuclear Engineering, 57-64, November 16–21, 1997

Paper No: IMECE1997-0607

DOI: https://doi.org/10.1115/IMECE1997-0607

View Paper

Topics: Emergencies, Simulation, Nuclear power stations, Safety, Accident management, Circuits, Computer simulation, Modeling, Pressure, Transients (Dynamics)

Proceedings Papers

Data Transfer From BETHSY 9.1B Experiment to Real NPP

Stojan Petelin, Borut Mavko, Igor Ravnikar, Yassin A. Hassan

Proc. ASME. IMECE97, Nuclear Engineering, 71-80, November 16–21, 1997

Paper No: IMECE1997-0609

DOI: https://doi.org/10.1115/IMECE1997-0609

View Paper

Topics: Nuclear power stations, Transients (Dynamics), Cooling systems, Engineering standards, Heat, Simulation, Test facilities

Proceedings Papers

Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA

Stojan Petelin, Borut Mavko, Mihael Jurkovic

Proc. ASME. IMECE97, Nuclear Engineering, 41-50, November 16–21, 1997

Paper No: IMECE1997-0605

DOI: https://doi.org/10.1115/IMECE1997-0605

View Paper

Topics: Boilers, Coolants, Nuclear power stations, Transients (Dynamics)

Proceedings Papers

Transient Three-Dimensional Density Distribution Reconstructed From Limited Interferogram Images

Koji Okamoto, Daigo Tsuru

Proc. ASME. IMECE98, Heat Transfer: Volume 5 — Numerical and Experimental Methods in Heat Transfer, 523-528, November 15–20, 1998

Paper No: IMECE1998-0771

DOI: https://doi.org/10.1115/IMECE1998-0771

View Paper

Topics: Density, Transients (Dynamics), Interferometers, Computers, Nuclear power stations, Optimization, Safety, Stratified flow

Proceedings Papers

Fluid Transient in a Voided System

Kalyan K. Niyogi, Robert R. Burdett, Steven Unikewicz

Proc. ASME. IMECE98, Fluids Engineering, 163-169, November 15–20, 1998

Paper No: IMECE1998-0999

DOI: https://doi.org/10.1115/IMECE1998-0999

View Paper

Topics: Collapse, Computer software, Computers, Condensation, Cooling, Flow (Dynamics), Fluids, Heat transfer, Nuclear power stations, Pipes

Proceedings Papers

Hydroaccumulator Influence on SB LOCA Transients at PMK-2 Test Facility

S. Petelin, I. Parzer

Proc. ASME. IMECE98, Nuclear Engineering, 31-36, November 15–20, 1998

Paper No: IMECE1998-1131

DOI: https://doi.org/10.1115/IMECE1998-1131

View Paper

Topics: Test facilities, Transients (Dynamics), Computers, High pressure (Physics), Nuclear power, Nuclear power stations, Simulation

Proceedings Papers

Evaluating the Implementation of Distributed Ledger Technology for the Licensing and Regulation of Nuclear Power Plants

Priyanka Pandit, Alp Tezbasaran, Arjun Earthperson, Mihai A. Diaconeasa

Proc. ASME. IMECE2021, Volume 8B: Energy, V08BT08A016, November 1–5, 2021

Paper No: IMECE2021-71730

DOI: https://doi.org/10.1115/IMECE2021-71730

View Paper

Topics: Licensing, Nuclear power stations

Proceedings Papers

On the Modeling of Wildfires-Induced Release and Atmospheric Dispersion in Radioactively Contaminated Regions

Damla Polat, Mihai A. Diaconeasa

Proc. ASME. IMECE2021, Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, V013T14A037, November 1–5, 2021

Paper No: IMECE2021-71460

DOI: https://doi.org/10.1115/IMECE2021-71460

View Paper

Topics: Modeling, Nuclear power stations, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Accidents, Fukushima nuclear disaster, Japan, 2011, Probabilistic risk assessment, Radiation (Physics), Emergency response, Fire, Combustion

Proceedings Papers

On the Use of Probabilistic Risk Assessment for the Protection of Small Modular Reactors Against Terrorist Attacks

Burak Polat, Mihai A. Diaconeasa

Proc. ASME. IMECE2021, Volume 13: Safety Engineering, Risk, and Reliability Analysis; Research Posters, V013T14A049, November 1–5, 2021

Paper No: IMECE2021-71504

DOI: https://doi.org/10.1115/IMECE2021-71504

View Paper

Topics: Probabilistic risk assessment, Small modular reactors, Terrorist attacks, Security, Human reliability analysis, Decision making, Computer software, Control rooms, Hazards, Nuclear industry

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

View Paper

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

Proceedings Papers

Fire Safety in Nuclear Power Plants: A Risk-Informed and Performance-Based Approach

Mohamed A. Azarm, Richard J. Travis

Proc. ASME. IMECE99, Safety Engineering and Risk Analysis, 79-86, November 14–19, 1999

Paper No: IMECE1999-1154

DOI: https://doi.org/10.1115/IMECE1999-1154

View Paper

Topics: Fire prevention, Nuclear power stations, Risk, Regulations, Decision making, Fire, Fire risk, Risk-based regulations

Proceedings Papers

Composite Materials Use: A Particular Case of Safety-Related Service Water Pipes

Th. Le Courtois, M. F. Pays

Proc. ASME. IMECE99, Advances in Aerospace Materials and Structures, 139-145, November 14–19, 1999

Paper No: IMECE1999-0142

DOI: https://doi.org/10.1115/IMECE1999-0142

View Paper

Topics: Composite materials, Safety, Water pipes, Manufacturing, Pipes, Design, Nondestructive evaluation, Nuclear power stations, Circuits, Corrosion

Proceedings Papers

Development of Pressurizer Transient Thermodynamics Analysis Code for Chashma Nuclear Power Plant

Arshad Mahmood, Xu Ji Jun

Proc. ASME. IMECE2001, Heat Transfer: Volume 2 — Heat Transfer in Multiphase Systems, 151-157, November 11–16, 2001

Paper No: IMECE2001/HTD-24164

DOI: https://doi.org/10.1115/IMECE2001/HTD-24164

View Paper

Topics: Computer software, Nuclear power stations, Pressure, Thermodynamics, Transients (Dynamics)

Proceedings Papers

Small Diameter Effects on Internal Flow Boiling

Gail E. Kendall, Peter Griffith, Arthur E. Bergles, John H. Lienhard, V

Proc. ASME. IMECE2001, Heat Transfer: Volume 3 — Fluid-Physics and Heat Transfer for Macro- and Micro-Scale Gas-Liquid and Phase-Change Flows, 153-169, November 11–16, 2001

Paper No: IMECE2001/HTD-24211

DOI: https://doi.org/10.1115/IMECE2001/HTD-24211

View Paper

Topics: Boiling, Computation, Critical heat flux, Design, Electrical conductance, Electronics, Flow (Dynamics), Flow instability, Heat transfer, HVAC equipment

Proceedings Papers

Analysis of the Flow Past a Pivoting Plate

Pascal Veber

Proc. ASME. IMECE2001, Fluids Engineering, 225-227, November 11–16, 2001

Paper No: IMECE2001/FED-24950

DOI: https://doi.org/10.1115/IMECE2001/FED-24950

View Paper

Topics: Flow (Dynamics), Water, Doors, Nuclear power stations, Pipes, Pressure, Safety, Steady state, Stress, Surface roughness

2 3 4

NARROW

Assessing the Potential for Implementation of Distributed Ledger Technology in the Nuclear Power Plant Lifecycle

Some Investigations on Flow Through Chevrons of Moisture Separator and Reheater Used in Nuclear Power Plants

Measurement of Two-Phase Mass Flow Rate and Quality Using Venturi and Void Fraction Meters

An Empirical Wear Projection Technology With Steam Generator Tube Applications and Relations to Work-Rate and Wear Simulations / Tests

Flow-Induced Vibration of a Tube Array in the Inlet Region of a High Performance Steam Generator: Part 1 — Turbulence Induced Vibration

Simulation of Some Emergency Operating Procedure for VVER-440 Reactors

Data Transfer From BETHSY 9.1B Experiment to Real NPP

Bethsy Test 6.9C Mid-Loop Operation Phenomena Identification Using RELAP5 NPA

Transient Three-Dimensional Density Distribution Reconstructed From Limited Interferogram Images

Fluid Transient in a Voided System

Hydroaccumulator Influence on SB LOCA Transients at PMK-2 Test Facility

Evaluating the Implementation of Distributed Ledger Technology for the Licensing and Regulation of Nuclear Power Plants

On the Modeling of Wildfires-Induced Release and Atmospheric Dispersion in Radioactively Contaminated Regions

On the Use of Probabilistic Risk Assessment for the Protection of Small Modular Reactors Against Terrorist Attacks

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

Fire Safety in Nuclear Power Plants: A Risk-Informed and Performance-Based Approach

Composite Materials Use: A Particular Case of Safety-Related Service Water Pipes

Development of Pressurizer Transient Thermodynamics Analysis Code for Chashma Nuclear Power Plant

Small Diameter Effects on Internal Flow Boiling

Analysis of the Flow Past a Pivoting Plate

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only