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Proceedings Papers

Uncertainty Analysis of RBMK-Related Experimental Data

Rolandas Urbonas, Algirdas Kaliatka, Mindaugas Liaukonis
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 801-807, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22490
https://doi.org/10.1115/ICONE10-22490
View Paper titled, Uncertainty Analysis of RBMK-Related Experimental Data
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Topics: Uncertainty analysis, Critical heat flux, Boundary-value problems, Flow instability, Heat, Simulation, Temperature, Test facilities, Uncertainty
Proceedings Papers

A Novel Molten Salt Reactor Concept to Implement the Multi-Step Time-Scheduled Transmutation Strategy

Gyula Csom, Sandor Feher, Mate Szieberth
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 891-898, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22688
https://doi.org/10.1115/ICONE10-22688
View Paper titled, A Novel Molten Salt Reactor Concept to Implement the Multi-Step Time-Scheduled Transmutation Strategy
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Topics: Molten salt reactors, Fuels, Circuits, Neutron flux, Radioactive wastes, Stress
Proceedings Papers

Radiation Induced Surface Activity Phenomenon: 2nd Report — Radiation Induced Boiling Enhancement

Tatsuya Koga, Yasuyuki Imai, Tomoji Takamasa, Koji Okamoto, Kaichiro Mishima
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 975-977, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22746
https://doi.org/10.1115/ICONE10-22746
View Paper titled, Radiation Induced Surface Activity Phenomenon: 2nd Report — Radiation Induced Boiling Enhancement
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Topics: Boiling, Critical heat flux, Metals, Radiation (Physics)
Proceedings Papers

Neutronic Analysis for Tehran Research Reactor Upgrading

Ebrahim Afshar, Alireza Shahidi
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 809-812, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22551
https://doi.org/10.1115/ICONE10-22551
View Paper titled, Neutronic Analysis for Tehran Research Reactor Upgrading
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Topics: Circuits, Cooling, Diffusion (Physics), Fuels, Neutron flux, Radioisotopes
Proceedings Papers

Characterization of Individual Fission Products in Terms of Their Production and Transmutation

Hiroshi Sagara, Tadashi Yoshida, Masaki Saito
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 1005-1009, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22753
https://doi.org/10.1115/ICONE10-22753
View Paper titled, Characterization of Individual Fission Products in Terms of Their Production and Transmutation
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Topics: Nuclear fission, Fast neutron reactors, Nuclides, Tin, Half-life, Hazards, Neutron sources, Nuclear power
Proceedings Papers

Comparison of a HCDA Numerical Simulation With the Results of the MARA 8 Test

M. F. Robbe, Y. Cariou, M. Lepareux, E. Treille
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 899-911, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22690
https://doi.org/10.1115/ICONE10-22690
View Paper titled, Comparison of a HCDA Numerical Simulation With the Results of the MARA 8 Test
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Topics: Accidents, Computer simulation, Countermeasures, Evacuations, Nuclear power stations, Safety
Proceedings Papers

Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments

Audrius Jasiulevicius, Bal Raj Sehgal
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 705-716, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22081
https://doi.org/10.1115/ICONE10-22081
View Paper titled, Validation of HELIOS Neutron Cross-Section Library for RBMK Reactors Against the Data From the Critical Facility Experiments
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Topics: Neutrons, Errors, Cross section (Physics), Fuels, Neutron flux, Dynamics (Mechanics), Graphite, Instrumentation, Nuclear power, Nuclear power stations
Proceedings Papers

Study of Mechanism of Initial Crud Formation on Fuel Cladding in Subcooled Boiling Region in PWR

Qinyang Rao, Barclay G. Jones
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 813-820, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22558
https://doi.org/10.1115/ICONE10-22558
View Paper titled, Study of Mechanism of Initial Crud Formation on Fuel Cladding in Subcooled Boiling Region in PWR
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Topics: Boiling, Bubbles, Cladding systems (Building), Flow (Dynamics), Fuels, Pressurized water reactors, Subcooling, Surface tension, Vapors, Diffusion (Physics)
Proceedings Papers

Application of Image Analysis With Noise Removal for Supercritical CO2

J. Ota, K. Sakurai, K. Okamoto, H. Madarame
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 1011-1016, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22755
https://doi.org/10.1115/ICONE10-22755
View Paper titled, Application of Image Analysis With Noise Removal for Supercritical CO2
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Topics: Noise (Sound), Supercritical carbon dioxide, Visualization, Supercritical fluids, Errors, Forced convection, Lasers, Nuclear reactors, Thermofluids, Water
Proceedings Papers

VIPRE02 Code Assesment for CHF and Post-CHF Heat Transfer Modes in Long Tubes

Audrius Jasiulevicius, Bal Raj Sehgal
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 717-726, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22082
https://doi.org/10.1115/ICONE10-22082
View Paper titled, VIPRE02 Code Assesment for CHF and Post-CHF Heat Transfer Modes in Long Tubes
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Topics: Critical heat flux, Heart failure, Heat transfer, Film boiling, Manufacturing, Nuclear fuels
Proceedings Papers

Modeling of Porous Crud Layer Based on Effects of Diffusion and Water Radiolysis on Anomalous Porous Crud Deposition on Fuel Pin Surfaces in PWRs

Hyun-Jong Joe, Barclay G. Jones
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 821-828, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22602
https://doi.org/10.1115/ICONE10-22602
View Paper titled, Modeling of Porous Crud Layer Based on Effects of Diffusion and Water Radiolysis on Anomalous Porous Crud Deposition on Fuel Pin Surfaces in PWRs
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Topics: Diffusion (Physics), Fuels, Modeling, Pressurized water reactors, Water
Proceedings Papers

The Effect of Numerical Diffusion on Oscillatory Flow in Two-Phase Boiling Channel

Chaiwat Muncharoen, Masanori Aritomi, Tatchai Sumitra, Takatoshi Takemoto
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 727-733, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22115
https://doi.org/10.1115/ICONE10-22115
View Paper titled, The Effect of Numerical Diffusion on Oscillatory Flow in Two-Phase Boiling Channel
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Topics: Boiling, Diffusion (Physics), Flow (Dynamics), Approximation, Boiling water reactors, Flow instability, Oscillations, Pressure drop
Proceedings Papers

Numerical Investigation of Bifurcation in Water Column Oscillator

K. Kawamata, Y. Morimoto, K. Okamoto, H. Madarame
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 1017-1023, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22756
https://doi.org/10.1115/ICONE10-22756
View Paper titled, Numerical Investigation of Bifurcation in Water Column Oscillator
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Topics: Bifurcation, Water, Valves, Noise (Sound), Numerical analysis
Proceedings Papers

One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool

William A. Wieselquist
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 913-919, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22694
https://doi.org/10.1115/ICONE10-22694
View Paper titled, One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool
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Topics: Computational fluid dynamics, Computer software, Turbulence, Air flow, Gas cooled reactors, Gas flow, Generation IV reactors, Heat flux, Pipes, Uncertainty
Proceedings Papers

Boron Concentration Model and Effects of Boron Holdup on Axial Offset Anomaly (AOA) in PWRs

Dawei Zhou, Barclay G. Jones
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 829-834, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22636
https://doi.org/10.1115/ICONE10-22636
View Paper titled, Boron Concentration Model and Effects of Boron Holdup on Axial Offset Anomaly (AOA) in PWRs
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Topics: Boron, Pressurized water reactors
Proceedings Papers

Quantifying the Metrics That Characterize Safety Culture of Three Engineered Systems

Julie Tucker, Mary Ernesti, Akira Tokuhiro
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 735-742, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22146
https://doi.org/10.1115/ICONE10-22146
View Paper titled, Quantifying the Metrics That Characterize Safety Culture of Three Engineered Systems
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Topics: Risk perception, Safety
Proceedings Papers

IEC-Based Neutron Generator for Security Inspection System

Linchun Wu, George H. Miley
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 921-926, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22696
https://doi.org/10.1115/ICONE10-22696
View Paper titled, IEC-Based Neutron Generator for Security Inspection System
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Topics: Inspection, Neutron generators, Neutrons, Security, X-rays, Explosives, Geometry, Ions, Neutron sources, Conceptual design
Proceedings Papers

Measurements of Bubble Rise Characteristics in Various Temperatures and Liquid Velocities

Kazuhiro Torimoto, Masanori Nishiura, Tomoe Tanaka, Tomio Okawa, Isao Kataoka
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 1025-1031, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22759
https://doi.org/10.1115/ICONE10-22759
View Paper titled, Measurements of Bubble Rise Characteristics in Various Temperatures and Liquid Velocities
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Topics: Bubbles, Temperature, Turbulence, Bubbly flow, Nuclear reactor safety, Pipes
Proceedings Papers

The Redistribution of Load in Bolted Gasketed Joints Subjected to Steady State Thermal Loading

Akli Nechache, Abdel-Hakim Bouzid
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 743-751, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22194
https://doi.org/10.1115/ICONE10-22194
View Paper titled, The Redistribution of Load in Bolted Gasketed Joints Subjected to Steady State Thermal Loading
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Topics: Steady state, Stress, Flanges, Temperature, Temperature effects, Design methodology, Finite element analysis, High temperature, Mechanical properties, Operating temperature
Proceedings Papers

Fundamental Experiments on Local Hydrogen Behaviors Under Severe Accident Conditions in a Rectangular Subcompartment of Nuclear Power Plant

Jung-Jae Lee, Un-Jang Lee, Goon-Cherl Park
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 835-843, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22637
https://doi.org/10.1115/ICONE10-22637
View Paper titled, Fundamental Experiments on Local Hydrogen Behaviors Under Severe Accident Conditions in a Rectangular Subcompartment of Nuclear Power Plant
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Topics: Accidents, Containment, Hydrogen, Nuclear power stations, Sprays