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Proceedings Papers

Investigation of Bleed-and-Feed Procedures for Mitigating the Consequence of a Total Loss-of-Feedwater Transient: IIST Experiments

C. H. Lee, T. J. Liu, C. Y. Chang, W. T. Hong, Y. K. Chan, I. M. Hwang, C. J. Chang
Proc. ASME. IMECE96, Thermal Science of Advanced Steam Generators/Heat Exchangers, 23-29, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0763
https://doi.org/10.1115/IMECE1996-0763
View Paper titled, Investigation of Bleed-and-Feed Procedures for Mitigating the Consequence of a Total Loss-of-Feedwater Transient: IIST Experiments
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Topics: Feedwater, Transients (Dynamics), Pressurized water reactors, Nuclear energy research, Nuclear reactor coolants, Pressure, Thermal hydraulics
Proceedings Papers

Stratification in Nuclear Reactor Components

J. A. Randorf, Y. A. Hassan
Proc. ASME. IMECE96, Thermal Science of Advanced Steam Generators/Heat Exchangers, 81-86, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0768
https://doi.org/10.1115/IMECE1996-0768
View Paper titled, Stratification in Nuclear Reactor Components
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Topics: Nuclear reactors, Accidents, Coolants, Junctions, Nuclear power, Nuclear reactor coolants, Safety, Simulation
Proceedings Papers

Experimental Study on PORV Stuck-Open Accident in INER Integral System Test Facility

T. J. Liu, C. H. Lee, W. T. Hong, Y. K. Chan, C. Y. Chang
Proc. ASME. IMECE96, Heat Transfer: Volume 3 — Experimental Studies in Multiphase Flow; Multiphase Flow in Porous Media; Experimental Multiphase Flows and Numerical Simulation of Two-Phase Flows; Fundamental Aspects of Experimental Methods, 123-130, November 17–22, 1996
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1996-0102
https://doi.org/10.1115/IMECE1996-0102
View Paper titled, Experimental Study on PORV Stuck-Open Accident in INER Integral System Test Facility
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Topics: Accidents, Test facilities, Cooling, High pressure (Physics), Loss of coolant accidents, Pressurized water reactors, Safety, Boilers, Emergency core cooling systems, Emergency operating procedures
Proceedings Papers

An Efficient Finite Element Method for the Representation of Fluid Structure Interaction in Large Structural Transient Dynamic Analyses

Alexander W. Harkness, Richard E. Schwirian
Proc. ASME. IMECE98, Fluids Engineering, 145-152, November 15–20, 1998
Publisher: American Society of Mechanical Engineers
Paper No: IMECE1998-0997
https://doi.org/10.1115/IMECE1998-0997
View Paper titled, An Efficient Finite Element Method for the Representation of Fluid Structure Interaction in Large Structural Transient Dynamic Analyses
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Topics: Dynamic analysis, Finite element methods, Fluid structure interaction, Transients (Dynamics), Fluids, Finite element analysis, Nuclear reactor coolants, Pressure, Accidents, Constraint equations
Proceedings Papers

Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors (SMRs)

Fatih Aydogan
Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A020, November 14–20, 2014
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2014-36415
https://doi.org/10.1115/IMECE2014-36415
View Paper titled, Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors (SMRs)
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Topics: Small modular reactors, Water, Safety, Nuclear power stations, Containment, Coolants, Emergencies, Nuclear fuels, Nuclear reactor coolants
Proceedings Papers

Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

Edwin A. Harvego, Michael G. McKellar
Proc. ASME. IMECE2011, Volume 4: Energy Systems Analysis, Thermodynamics and Sustainability; Combustion Science and Engineering; Nanoengineering for Energy, Parts A and B, 75-81, November 11–17, 2011
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2011-63073
https://doi.org/10.1115/IMECE2011-63073
View Paper titled, Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications
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Topics: Cycles, Optimization, Power stations, Supercritical carbon dioxide, Temperature, Carbon dioxide, Heat, Pressure, Thermal efficiency, Very high temperature reactors
Proceedings Papers

Measurements and Code Comparisons for Advanced Gas Reactor Coolant Channels Containing Spacer Ribs

Glenn E. McCreery, Thomas D. Foust, Donald M. McEligot, Keith G. Condie, Robert J. Pink
Proc. ASME. IMECE2002, Heat Transfer, Volume 4, 107-113, November 17–22, 2002
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2002-33597
https://doi.org/10.1115/IMECE2002-33597
View Paper titled, Measurements and Code Comparisons for Advanced Gas Reactor Coolant Channels Containing Spacer Ribs
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Topics: Annulus, Computation, Coolants, Flow (Dynamics), Forced convection, Gas cooled reactors, Heat transfer, High temperature, Lasers, Nuclear reactor coolants
Proceedings Papers

Overall Review of Steam Jet Condensation in a Next Generation Reactor Water Pool

Yeon-Sik Kim, Chul-Hwa Song
Proc. ASME. IMECE2003, Heat Transfer, Volume 4, 129-138, November 15–21, 2003
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2003-42425
https://doi.org/10.1115/IMECE2003-42425
View Paper titled, Overall Review of Steam Jet Condensation in a Next Generation Reactor Water Pool
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Topics: Condensation, Steam, Water, Design, Pressurized water reactors, Safety, Stress, Feedwater, Flow (Dynamics), Heat transfer coefficients