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Proceedings Papers

VVER-440 Containment Thermal Hydraulic Analyses With MELCOR and CONTAIN Codes

Gregory Gromov, Igor Lola, Stanislav Sholomitsky, Dmitry Gumenyuk, Valery Shikhabutinov, Yury Alekseev, K. C. Wagner, Jack Dallman
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 447-454, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22705
https://doi.org/10.1115/ICONE10-22705
View Paper titled, VVER-440 Containment Thermal Hydraulic Analyses With MELCOR and CONTAIN Codes
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Topics: Containment, Accidents, Design, Coolants, Pressure, Safety, Temperature, Boundary-value problems, Bubbles, Condensers (steam plant)
Proceedings Papers

Some Issues of Electrical Systems Modeling in Course of PSA

Michael Lankin
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 349-355, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22547
https://doi.org/10.1115/ICONE10-22547
View Paper titled, Some Issues of Electrical Systems Modeling in Course of PSA
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Topics: Electronic systems, Modeling, Nuclear power stations, Electricity (Physics)
Proceedings Papers

Steam Generator Replacement and Power Uprating on Tihange 2 Nuclear Plant: Safety Study Analyses

Andre´ Malaval, Pascale Marin-Lafle`che, Myriam Forgeot d’Arc, Ce´line Collin
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 159-164, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22263
https://doi.org/10.1115/ICONE10-22263
View Paper titled, Steam Generator Replacement and Power Uprating on Tihange 2 Nuclear Plant: Safety Study Analyses
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Topics: Boilers, Nuclear power stations, Power uprate, Safety
Proceedings Papers

Study of a Station Blackout Event in the PWR Plant

Ching-Hui Wu, Tsu-Jen Lin, Tsu-Mu Kao
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 455-460, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22757
https://doi.org/10.1115/ICONE10-22757
View Paper titled, Study of a Station Blackout Event in the PWR Plant
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Topics: Pressurized water reactors, Probabilistic risk assessment, Emergencies, Nuclear power stations, Trains, Cycles, Design, Diesel generators, Explosions, Fire
Proceedings Papers

Experimental Study and Analytical Methods for Particle Bed Dryout With Heterogeneous Particles and Pressure Variation

Jaakko Miettinen, Risto Sairanen, Stefan Holmstrom, Ilona Lindholm
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 255-269, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22420
https://doi.org/10.1115/ICONE10-22420
View Paper titled, Experimental Study and Analytical Methods for Particle Bed Dryout With Heterogeneous Particles and Pressure Variation
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Topics: Analytical methods, Particulate matter, Pressure, Transients (Dynamics), Critical heat flux, Heat flux, Accident management, Accidents, Containment, Cooling
Proceedings Papers

Pre-Operational Seismic Walk-Through of NPPs in India

R. S. Soni, R. K. Mishra, M. K. Agrawal, G. R. Reddy, H. S. Kushwaha, V. Venkat Raj, G. Badrinarayan, R. V. Hawaldar, S. M. Ingole
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 357-363, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22567
https://doi.org/10.1115/ICONE10-22567
View Paper titled, Pre-Operational Seismic Walk-Through of NPPs in India
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Topics: Nuclear power stations, Safety, Design, Construction, Earthquakes
Proceedings Papers

RBMK Safety Analysis in Accidents Initiated by Partial Ruptures of the Circulation Circuit

Anatoly I. Dostov, Alexander Ja. Kramerov
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 165-171, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22273
https://doi.org/10.1115/ICONE10-22273
View Paper titled, RBMK Safety Analysis in Accidents Initiated by Partial Ruptures of the Circulation Circuit
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Topics: Accidents, Circuits, Rupture, Safety, Cladding systems (Building), Fuel rods, Temperature, Uncertainty
Proceedings Papers

Systematic Source Term Analyses for Level 3 PSA of a BWR With Mark-II Type Containment With THALES-2 Code

Jun Ishikawa, Ken Muramatsu, Toru Sakamoto
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 87-94, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22080
https://doi.org/10.1115/ICONE10-22080
View Paper titled, Systematic Source Term Analyses for Level 3 PSA of a BWR With Mark-II Type Containment With THALES-2 Code
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Topics: Accidents, Boiling water reactors, Containment, Failure, Failure mechanisms
Proceedings Papers

Practical Approaches to Addressing the Evolving Perception of Terrorist Threats to Nuclear Power Plants

E. J. Butcher, J. W. Roe
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 461-464, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22761
https://doi.org/10.1115/ICONE10-22761
View Paper titled, Practical Approaches to Addressing the Evolving Perception of Terrorist Threats to Nuclear Power Plants
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Topics: Nuclear power stations, Governments, Terrorist attacks
Proceedings Papers

How Good Is Good: Improved Tracking and Managing of Safety Goals, Performance Indicators, Production Targets and Significant Events Using Learning Curves

Romney B. Duffey, John W. Saull
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 271-280, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22426
https://doi.org/10.1115/ICONE10-22426
View Paper titled, How Good Is Good: Improved Tracking and Managing of Safety Goals, Performance Indicators, Production Targets and Significant Events Using Learning Curves
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Topics: Safety, Aircraft, Engineering disciplines, Errors, Maintenance, Nuclear power stations, Statistics, Stress
Proceedings Papers

Analysis of a CRDM Nozzle Break LOCA Without Scram Using the U.S. NRC Coupled Code TRAC-M/PARCS

A. Cuadra, J. Ragusa, T. Downar, K. Ivanov
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 365-374, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22579
https://doi.org/10.1115/ICONE10-22579
View Paper titled, Analysis of a CRDM Nozzle Break LOCA Without Scram Using the U.S. NRC Coupled Code TRAC-M/PARCS
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Topics: Nozzles, Scram, Transients (Dynamics), Control systems, Fracture (Materials), Accidents, Coolants, Emergency core cooling systems, Failure, Nuclear power stations
Proceedings Papers

Reliability Methods for Passive Safety Functions

M. Marque`s, J. F. Pignatel, F. D’Auria, L. Burgazzi, C. Mu¨ller, G. Cojazzi, V. La Lumia
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 173-180, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22274
https://doi.org/10.1115/ICONE10-22274
View Paper titled, Reliability Methods for Passive Safety Functions
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Topics: Reliability, Safety, Computation, Computers, Condensers (steam plant), Sensitivity analysis, Uncertainty
Proceedings Papers

Fuel Rod Melt Progression Simulation Using Low-Temperature Melting Metal Alloy

Seung Dong Lee, Kune Y. Suh, GoonCherl Park, Un Chul Lee
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 281-286, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22437
https://doi.org/10.1115/ICONE10-22437
View Paper titled, Fuel Rod Melt Progression Simulation Using Low-Temperature Melting Metal Alloy
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Topics: Alloys, Fuel rods, Low temperature, Melting, Simulation, Damage, Film flow, Film thickness, Flow (Dynamics), Heating
Proceedings Papers

U.S. Department of Energy Sponsored In-Depth Safety Assessments of VVER and RBMK Reactors

Mark C. Petri, Walter F. Pasedag
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 375-379, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22586
https://doi.org/10.1115/ICONE10-22586
View Paper titled, U.S. Department of Energy Sponsored In-Depth Safety Assessments of VVER and RBMK Reactors
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Topics: Safety, Nuclear power stations, Risk, Security
Proceedings Papers

Inaccurate Use of Boron Concentration for Reactivity Feedback

Birol Aktas, Sule Ergun
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 181-185, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22298
https://doi.org/10.1115/ICONE10-22298
View Paper titled, Inaccurate Use of Boron Concentration for Reactivity Feedback
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Topics: Boron, Feedback, Transients (Dynamics), Coolants, Density, Failure, Pressurized water reactors, Scram
Proceedings Papers

RELAP5/MOD3.2 Investigation of a VVER-1000 MCP Switching on Problem

Pavlin Groudev, Malinka Pavlova
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 287-294, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22443
https://doi.org/10.1115/ICONE10-22443
View Paper titled, RELAP5/MOD3.2 Investigation of a VVER-1000 MCP Switching on Problem
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Topics: Computers, Coolants, Design, Feedback, Flow (Dynamics), Neutrons, Nuclear power, Nuclear power stations, Nuclear reactors, Nuclear research
Proceedings Papers

History of Fire Events in the U.S. Commercial Nuclear Industry

Bijan Najafi, Robert P. Kassawara, Francisco Joglar-Biloch, Yehia Khalil
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 381-388, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22587
https://doi.org/10.1115/ICONE10-22587
View Paper titled, History of Fire Events in the U.S. Commercial Nuclear Industry
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Topics: Fire, Nuclear industry, Risk, Data collection, Databases, Fire risk, Nuclear power stations, Boiling water reactors, Cables, Electricity (Physics)
Proceedings Papers

Reliability Analysis of Cooling Towers: Influence of Rebars Corrosion on Failure

Bruno Sudret, Maurice Pendola
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 115-121, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22136
https://doi.org/10.1115/ICONE10-22136
View Paper titled, Reliability Analysis of Cooling Towers: Influence of Rebars Corrosion on Failure
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Topics: Cooling towers, Corrosion, Event history analysis, Failure, Reinforced concrete
Proceedings Papers

Applying U.S. EOP Analytical Justification Experience for VVER Plants in the Ukraine

Paul A. Linn, Harold V. Julian, James R. Chapman, Alexander Trifanov, Oleg Zhabin, Sergey Fedorchenko, Alexander Rybchuk
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 415-422, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22640
https://doi.org/10.1115/ICONE10-22640
View Paper titled, Applying U.S. EOP Analytical Justification Experience for VVER Plants in the Ukraine
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Topics: Accidents, Architects, Design, Emergencies, Emergency response, Engineers, Failure, High pressure (Physics), Licensing, Nuclear power stations
Proceedings Papers

An Approach of Uncertainty Evaluation for Thermal-Hydraulic Analysis

Katsunori Ogura, Hisashi Ninokata
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 81-86, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22062
https://doi.org/10.1115/ICONE10-22062
View Paper titled, An Approach of Uncertainty Evaluation for Thermal-Hydraulic Analysis
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Topics: Uncertainty, Turbines