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Pavel Kudinov
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Proceedings Papers

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A084, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65751
https://doi.org/10.1115/ICONE28-65751
View Paper titled, Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model
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Topics: Condensation, Environmental health and safety, Momentum, Steam, Thermal stratification, Turbulence, Heat, Boundary-value problems, Containment, Modeling
Proceedings Papers

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers Using a Condensation Region Approach

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T03A025, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16852
https://doi.org/10.1115/ICONE2020-16852
View Paper titled, Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers Using a Condensation Region Approach
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Topics: Computational fluid dynamics, Condensation, Momentum, Steam, Thermal stratification
Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.
Paper No: NERS-19-1170
https://doi.org/10.1115/1.4047552
Published Online: September 4, 2020
View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty
Journal Articles

Safest Roadmap for Corium Experimental Research in Europe

Christophe Journeau, Viviane Bouyer, Nathalie Cassiaut-Louis, Pascal Fouquart, Pascal Piluso, Gérard Ducros, Stéphane Gossé, Christine Guéneau, Andrea Quaini, Beatrix Fluhrer, Alexei Miassoedov, Juri Stuckert, Martin Steinbrück, Sevostian Bechta, Pavel Kudinov, Weimin Ma, Bal Raj Sehgal, Zoltan Hozer, Attila Guba, Dario Manara, David Bottomley, Manfred Fischer, Gert Langrock, Holger Schmidt, Monika Kiselova, Jiri Ždarek
Journal: ASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg
Publisher: ASME
Article Type: Research-Article
ASME J. Risk Uncertainty Part B. September 2018, 4(3): 030901.
Paper No: RISK-16-1145
https://doi.org/10.1115/1.4037878
Published Online: December 5, 2017
View Article titled, Safest Roadmap for Corium Experimental Research in Europe
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Water, Safety, Explosions, Nuclear power stations, Reactor vessels, Vessels, Fuels, Steam
Proceedings Papers

SAFEST Roadmap for Corium Experimental Research in Europe

Christophe Journeau, Viviane Bouyer, Nathalie Cassiaut-Louis, Pascal Fouquart, Pascal Piluso, Gérard Ducros, Stéphane Gossé, Christine Guéneau, Andrea Quaini, Beatrix Fluhrer, Alexei Miassoedov, Juri Stuckert, Martin Steinbrück, Sevostian Bechta, Pavel Kudinov, Zoltan Hozer, Attila Guba, Dario Manara, David Bottomley, Manfred Fischer, Gert Langrock, Holger Schmidt, Monika Kiselova, Jiri Ždarek
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T14A019, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60916
https://doi.org/10.1115/ICONE24-60916
View Paper titled, SAFEST Roadmap for Corium Experimental Research in Europe
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Topics: Accidents, Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Reactor vessels, Safety, Spent nuclear fuels, Stress
Proceedings Papers

A Model for Prediction of Maximum Post-Dryout Temperature in Decay-Heated Debris Bed

Sergey E. Yakush, Pavel Kudinov
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A057, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31214
https://doi.org/10.1115/ICONE22-31214
View Paper titled, A Model for Prediction of Maximum Post-Dryout Temperature in Decay-Heated Debris Bed
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Topics: Temperature, Cooling, Boiling water reactors, Computer simulation, Safety, Accident management, Accidents, Flow (Dynamics), Heat, Light water reactors
Proceedings Papers

Risk-Informed Approach to Debris Bed Coolability Issue

Sergey E. Yakush, Nazar T. Lubchenko, Pavel Kudinov
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 531-543, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55186
https://doi.org/10.1115/ICONE20-POWER2012-55186
View Paper titled, Risk-Informed Approach to Debris Bed Coolability Issue
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Topics: Risk, Heat flux, Accidents, Probability, Stress, Engineering simulation, Failure, Flux (Metallurgy), Heat, Risk analysis
Proceedings Papers

Effect of CRGT Cooling on Modes of Global Vessel Failure of a BWR Lower Head

Walter Villanueva, Chi-Thanh Tran, Pavel Kudinov
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 467-477, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54955
https://doi.org/10.1115/ICONE20-POWER2012-54955
View Paper titled, Effect of CRGT Cooling on Modes of Global Vessel Failure of a BWR Lower Head
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Topics: Boiling water reactors, Cooling, Failure, Vessels, Creep, Reactor vessels, Delays, Stress, Thermomechanics, Accidents