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Proceedings Papers

Modeling of QUENCH 10 Experiment on Air Ingress Using RELAP/SCDAPSIM Mod 3.5

Tadas Kaliatka, Eugenijus Uspuras, Chris M. Allison
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A007, July 2–6, 2017
Paper No: ICONE25-66135
DOI: https://doi.org/10.1115/ICONE25-66135
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Topics: Accident management, Accidents, Computers, Light water reactors, Modeling, Oxidation, Steam, Transients (Dynamics), Water, Zirconium
Proceedings Papers

Modelling of Water Ingress in to Vacuum Vessel

Tadas Kaliatka, Eugenijus Ušpuras, Algirdas Kaliatka
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A007, July 7–11, 2014
Paper No: ICONE22-30865
DOI: https://doi.org/10.1115/ICONE22-30865
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Topics: Modeling, Vacuum, Vessels, Water, Coolants, Accidents, Pressure, Nuclear fusion, Transients (Dynamics), Cooling systems
Proceedings Papers

Modelling of QUENCH 03 and QUENCH 06 Experiments Using RELAP/SCDAPSIM Code

Tadas Kaliatka, Eugenijus Ušpuras, Algirdas Kaliatka
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A020, July 29–August 2, 2013
Paper No: ICONE21-15894
DOI: https://doi.org/10.1115/ICONE21-15894
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Topics: Modeling, Accidents, Floods, Light water reactors, Accident management, Computers, Coolants, Electricity (Physics), Fuel rods, Fuels
Proceedings Papers

Best Estimate Analysis of PHEBUS FPT1 Test Using RELAP/SCDAPSIM Code

Tadas Kaliatka, Eugenijus Ušpuras, Virginijus Vileiniškis
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 411-418, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54693
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54693
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Topics: Accidents, Aerosols, Chemistry, Computers, Fuels, Melting, Nuclear fission, Nuclear reactors, Sensitivity analysis, Simulation
Proceedings Papers

Effect of Spacer Grids on the Local Heat Transfer

Benediktas Cesna, Eugenijus Uspuras
Proc. ASME. IHTC14, 2010 14th International Heat Transfer Conference, Volume 4, 523-528, August 8–13, 2010
Paper No: IHTC14-22589
DOI: https://doi.org/10.1115/IHTC14-22589
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Topics: Heat transfer
Proceedings Papers

Problems With Cooling of Overheated Fuel Channels in RBMK-Type Reactors

Eugenijus Uspuras, Algirdas Kaliatka
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 617-625, May 11–15, 2008
Paper No: ICONE16-48266
DOI: https://doi.org/10.1115/ICONE16-48266
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Topics: Cooling, Fuels, Accident management, Accidents, Water, Circuits, Design, Heat, Light water reactors, Nuclear power stations
Proceedings Papers

RELAP5-3D Code Application for RBMK-1500 Reactor Core Analysis

Evaldas Bubelis, Algirdas Kaliatka, Eugenijus Uspuras
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 757-765, April 14–18, 2002
Paper No: ICONE10-22450
DOI: https://doi.org/10.1115/ICONE10-22450
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Topics: Nuclear power stations, Transients (Dynamics)
Proceedings Papers

Evaluation of Pipe Whip Impacts on Neighboring Piping and Walls of the Ignalina Nuclear Power Plant

Gintautas Dundulis, Ronald F. Kulak, Algirdas Marchertas, Evaldas Narvydas, Mark C. Petry, Eugenijus Uspuras
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 673-681, April 14–18, 2002
Paper No: ICONE10-22469
DOI: https://doi.org/10.1115/ICONE10-22469
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Topics: Nuclear power stations, Pipes, Emergency core cooling systems, Accidents, Finite element analysis, Concrete walls, Coolants, Damage, Failure, Pipelines
Proceedings Papers

RELAP5-3D Code Validation for RBMK-1500 Reactors

Evaldas Bubelis, Algirdas Kaliatka, Eugenijus Uspuras
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 429-438, April 25–29, 2004
Paper No: ICONE12-49122
DOI: https://doi.org/10.1115/ICONE12-49122
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Topics: Circuits, Modeling, Nuclear power stations, Safety, Transients (Dynamics)
Proceedings Papers

The Specifics of RBMK Core Cooling at Overheated Conditions

Eugenijus Uspuras, Egidijus Urbonavicius, Algirdas Kaliatka
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 345-353, July 17–20, 2006
Paper No: ICONE14-89337
DOI: https://doi.org/10.1115/ICONE14-89337
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Topics: Accidents, Alloys, Boiling, Cooling, Design, Flow (Dynamics), Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

Degradation Assessment in Complex Systems

Vaidas Matuzas, Juozas Augutis, Eugenijus Uspuras
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 533-536, July 17–20, 2006
Paper No: ICONE14-89190
DOI: https://doi.org/10.1115/ICONE14-89190
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Topics: Complex systems, Reliability, Failure, Nuclear power stations, Risk assessment, Wear
Proceedings Papers

Ignalina NPP Unit 2 Gas Gap Probabilistic Evaluation

Jurgita Simaityte Volskiene, Juozas Augutis, Eugenijus Uspuras
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 637-640, July 17–20, 2006
Paper No: ICONE14-89478
DOI: https://doi.org/10.1115/ICONE14-89478
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Topics: Nuclear power stations, Graphite, Pressure, Probability, Maintenance, Masonry, Service life (Equipment)
eBook Chapter

Probabilistic Modeling of Aircraft Crash and Impact on Ignalina NPP Considering Uncertainty (PSAM-0471)

Series: ASME Press Select Proceedings
Publisher: ASME Press
Published: 2006
ISBN-10: 0791802442
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Topics: Aircraft, Modeling, Nuclear power stations, Uncertainty
eBook Chapter

Risk Management of Hazardous Materials Transportation (PSAM-0464)

Series: ASME Press Select Proceedings
Publisher: ASME Press
Published: 2006
ISBN-10: 0791802442
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Topics: Hazardous substances, Risk management, Transportation systems