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Proceedings Papers

A Statistical Model for Accessing Wall Thinning Rate due to Flow Accelerated Corrosion Based on Inspection Data in Nuclear Power Plants

Yuyun Zeng, Jingquan Liu, Weilin Huang
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, V001T01A001, July 7–11, 2014
Paper No: ICONE22-30043
DOI: https://doi.org/10.1115/ICONE22-30043
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Topics: Corrosion, Flow (Dynamics), Inspection, Nuclear power stations, Pipes, Pressurized water reactors, Alloys, Carbon steel, Circuits, Decision making
Proceedings Papers

Methodology for Identification of the Coolant Thermalhydraulic Regimes in the Core of Nuclear Reactors

L. G. Sharaevsky, E. I. Sharaevskaya, E. D. Domashev, A. P. Arkhypov, V. N. Kolochko
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 91, April 14–18, 2002
Paper No: ICONE10-22386
DOI: https://doi.org/10.1115/ICONE10-22386
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Topics: Accidents, Acoustics, Algorithms, Boiling, Bubbles, Coolants, Dimensions, Flow (Dynamics), Fuels, Heat transfer
Proceedings Papers

Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance

E. Kevin Doyle
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 1-9, April 14–18, 2002
Paper No: ICONE10-22011
DOI: https://doi.org/10.1115/ICONE10-22011
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Topics: Complex systems, Containment, Design, Engineers, Errors, Failure, Failure data, Maintenance, Nuclear power, Nuclear power plant maintenance
Proceedings Papers

Wavelet Analysis on Eddy Structure in Micro Bubble Two Phase Flow Using PIV

Ling Zhen, Claudia del Carmen Gutierrez-Torres
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 871-874, April 25–29, 2004
Paper No: ICONE12-49585
DOI: https://doi.org/10.1115/ICONE12-49585
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Topics: Eddies (Fluid dynamics), Microbubbles, Two-phase flow, Wavelets, Turbulence, Drag reduction, Boundary layers, Vortices, Containment, Drag (Fluid dynamics)
Proceedings Papers

A Methodology for Discerning Incipient Boiling of the Coolant in a Water-Moderated, Water-Cooled (Pressurized-Water) Nuclear Reactor by Means of the Bayesian Neutron-Noise Classifier

Igor Sharayevskij
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 661-668, July 17–20, 2006
Paper No: ICONE14-89630
DOI: https://doi.org/10.1115/ICONE14-89630
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Topics: Boiling, Coolants, Neutrons, Noise (Sound), Nuclear reactors, Water, Algorithms, Neutron flux, Nuclear power stations, Pressure
Proceedings Papers

The Use of ARMA Models in Earthquake Response Spectra

Malek Brahimi, Sidi Berri
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 7-13, July 17–20, 2006
Paper No: ICONE14-89023
DOI: https://doi.org/10.1115/ICONE14-89023
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Topics: Earthquakes, Spectra (Spectroscopy), Displacement, Ductility, Degrees of freedom, Excitation, Modeling, Stiffness, Stochastic processes, Structural design