Publikationer av Pavel Kudinov

Refereegranskade

Artiklar

[1]

S. Paranjape et al., "Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection," Nuclear Engineering and Design, vol. 419, 2024.

[2]

K. W. Wong et al., "Hydrodynamic design of the Separate Effect test facility for Flow-Accelerated Corrosion and Erosion (SEFACE) studies in liquid lead," Nuclear Engineering and Design, vol. 417, 2024.

[3]

X. Wang, D. Grishchenko och P. Kudinov, "Simulation of jets induced by steam injection through multi-hole sparger using effective heat and momentum models," Nuclear Engineering and Design, vol. 405, 2023.

[4]

C. R. Hernandez et al., "Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor," Nuclear Engineering and Design, vol. 392, s. 111773, 2022.

[5]

S. Thakre et al., "Experimental investigation of solid particle spreading driven by gas injection into a pool of water," Annals of Nuclear Energy, vol. 174, s. 109165-109165, 2022.

[6]

X. Wang, D. Grishchenko och P. Kudinov, "Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility," Nuclear Engineering and Design, vol. 386, 2022.

[7]

S. Galushin, D. Grishchenko och P. Kudinov, "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 roaam1 framework," Journal of Nuclear Engineering and Radiation Science, vol. 6, no. 4, 2020.

[8]

S. Galushin, D. Grishchenko och P. Kudinov, "Implementation of framework for assessment of severe accident management effectiveness in Nordic BWR," Reliability Engineering & System Safety, vol. 203, 2020.

[9]

S. Estévez-Albuja et al., "Modelling of a Nordic BWR containment and suppression pool behavior during a LOCA with GOTHIC 8.1," Annals of Nuclear Energy, vol. 136, 2020.

[10]

A. Papukchiev, D. Grishchenko och P. Kudinov, "On the need for conjugate heat transfer modeling in transient CFD simulations," Nuclear Engineering and Design, vol. 367, 2020.

[11]

S. Galushin och P. Kudinov, "Sensitivity and Uncertainty Analysis of the Vessel Lower Head Failure Mode and Melt Release Conditions in Nordic BWR using MELCOR Code," Annals of Nuclear Energy, vol. 135, 2020.

[12]

D. Grishchenko et al., "TALL-3D open and blind benchmark on natural circulation instability," Nuclear Engineering and Design, vol. 358, 2020.

[13]

S. Galushin och P. Kudinov, "Analysis of the Effect of MELCOR Modelling Parameters on In-Vessel Accident Progression in Nordic BWR," Nuclear Engineering and Design, vol. 350, s. 243-258, 2019.

[14]

S. Galushin och P. Kudinov, "Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code," Science and Technology of Nuclear Installations, 2019.

[15]

I. Gallego-Marcos et al., "Effective momentum induced by steam condensation in the oscillatory bubble regime," International Journal of Multiphase Flow, vol. 350, s. 259-274, 2019.

[16]

D. Grishchenko, S. Galushin och P. Kudinov, "Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a Nordic type BWR," Nuclear Engineering and Design, vol. 343, s. 63-75, 2019.

[17]

S. E. Yakush och P. Kudinov, "On the evaluation of dryout conditions for a heat-releasing porous bed in a water pool," International Journal of Heat and Mass Transfer, s. 895-905, 2019.

[18]

V. Moreau et al., "Pool CFD modelling : lessons from the SESAME project," Nuclear Engineering and Design, vol. 355, 2019.

[19]

I. Gallego-Marcos et al., "Pool stratification and mixing induced by steam injection through spargers : CFD modelling of the PPOOLEX and PANDA experiments," Nuclear Engineering and Design, vol. 347, s. 67-85, 2019.

[20]

I. Gallego-Marcos, D. Grishchenko och P. Kudinov, "Thermal stratification and mixing in a Nordic BWR pressure suppression pool," Annals of Nuclear Energy, vol. 132, s. 442-450, 2019.

[21]

M. Jeltsov, D. Grishchenko och P. Kudinov, "Validation of Star-CCM plus for liquid metal thermal-hydraulics using TALL-3D experiment," Nuclear Engineering and Design, vol. 341, s. 306-325, 2019.

[22]

I. Gallego Marcos, W. Villanueva och P. Kudinov, "Modelling of pool stratification and mixing induced by steam injectionthrough blowdown pipes," Annals of Nuclear Energy, vol. 112, s. 624-639, 2018.

[23]

I. Gallego-Marcos et al., "Pool stratification and mixing during a steam injection through spargers: analysis of the PPOOLEX and PANDA experiments," Nuclear Engineering and Design, vol. 337, s. 300-316, 2018.

[24]

M. Jeltsov et al., "Pre-test analysis of an LBE solidification experiment in TALL-3D," Nuclear Engineering and Design, vol. 339, s. 21-38, 2018.

[25]

V.-A. Phung et al., "Prediction of In-Vessel Debris Bed Properties in BWR Severe Accident Scenarios using MELCOR and Neural Networks," Annals of Nuclear Energy, s. 461-476, 2018.

[26]

C. Journeau et al., "Safest roadmap for corium experimental research in Europe," ASCE-ASME J of Risk & Uncertainty in Engineering Systems Part B : Mechanical Engineering, vol. 4, no. 3, 2018.

[27]

M. Jeltsov, W. Villanueva och P. Kudinov, "Seismic sloshing effects in lead-cooled fast reactors," Nuclear Engineering and Design, vol. 332, s. 99-110, 2018.

[28]

S. Galushin och P. Kudinov, "Sensitivity analysis of debris properties in lower plenum of a Nordic BWR," Nuclear Engineering and Design, vol. 332, s. 374-382, 2018.

[29]

M. Jeltsov, W. Villanueva och P. Kudinov, "Steam generator leakage in lead cooled fast reactors : Modeling of void transport to the core," Nuclear Engineering and Design, vol. 328, s. 255-265, 2018.

[30]

H. Li et al., "Thermal stratification and mixing in a suppression pool induced by direct steam injection," Annals of Nuclear Energy, vol. 111, s. 487-498, 2018.

[31]

A. Konovalenko et al., "Controllable Generation of a Submillimeter Single Bubble in Molten Metal Using a Low-Pressure Macrosized Cavity," Metallurgical and materials transactions. B, process metallurgy and materials processing science, vol. 48, no. 2, s. 1064-1072, 2017.

[32]

K. Kööp et al., "Pre-test analysis for identification of natural circulation instabilties in TALL-3D facility," Nuclear Engineering and Design, vol. 314, s. 110-120, 2017.

[33]

P. Kudinov et al., "Premixing and steam explosion phenomena in the tests with stratified melt-coolant configuration and binary oxidic melt simulant materials," Nuclear Engineering and Design, vol. 314, s. 182-197, 2017.

[34]

S. Galushin och P. Kudinov, "Analysis of core degradation and relocation phenomena and scenarios in a Nordic-type BWR," NUCLEAR ENGINEERING AND DESIGN, vol. 310, s. 125-141, 2016.

[35]

V.-A. Phung et al., "Automation of RELAP5 input calibration and code validation using genetic algorithm," Nuclear Engineering and Design, vol. 300, s. 210-221, 2016.

[36]

V.-A. Phung et al., "Characteristics of debris in the lower head of a BWR in different severe accident scenarios," Nuclear Engineering and Design, vol. 305, s. 359-370, 2016.

[37]

D. Grishchenko, S. Basso och P. Kudinov, "Development of a surrogate model for analysis of ex-vessel steam explosion in Nordic type BWRs," NUCLEAR ENGINEERING AND DESIGN, vol. 310, s. 311-327, 2016.

[38]

S. Basso, A. Konovalenko och P. Kudinov, "Effectiveness of the debris bed self-leveling under severe accident conditions," Annals of Nuclear Energy, vol. 95, s. 75-85, 2016.

[39]

S. Basso, A. Konovalenko och P. Kudinov, "Empirical closures for particulate debris bed spreading induced by gas-liquid flow," Nuclear Engineering and Design, vol. 297, s. 19-25, 2016.

[40]

A. Konovalenko et al., "Experimental investigation of particulate debris spreading in a pool," Nuclear Engineering and Design, vol. 297, s. 208-219, 2016.

[41]

L. Manickam et al., "On the influence of water subcooling and melt jet parameters on debris formation," Nuclear Engineering and Design, vol. 309, s. 265-276, 2016.

[42]

S. Basso et al., "The effect of self-leveling on debris bed coolability under severe accident conditions," Nuclear Engineering and Design, vol. 305, s. 246-259, 2016.

[43]

G. Bandini et al., "Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors," Nuclear Engineering and Design, vol. 281, s. 22-38, 2015.

[44]

A. Papukchiev et al., "Comparison of different coupling CFD-STH approaches for pre-test analysis of a TALL-3D experiment," Nuclear Engineering and Design, vol. 290, s. 135-143, 2015.

[45]

R. Kumar et al., "Dynamic Hybrid Reliability Studies of a Decay Heat Removal System," International Journal of Reliability, Quality and Safety Engineering (IJRQSE), vol. 22, no. 4, 2015.

[46]

W. Villanueva et al., "Generalization of experimental data on amplitude and frequency of oscillations induced by steam injection into a subcooled pool," Nuclear Engineering and Design, vol. 295, s. 155-161, 2015.

[47]

V.-A. Phung et al., "Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability," Science and Technology of Nuclear Installations, vol. 2015, s. 1-14, 2015.

[48]

M. Jeltsov, W. Villanueva och P. Kudinov, "Parametric study of sloshing effects in the primary system of an isolated lead-cooled fast reactor," Nuclear Technology, vol. 190, no. 1, s. 1-10, 2015.

[49]

V.-A. Phung och P. Kudinov, "Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes," Science and Technology of Nuclear Installations, 2015.

[50]

S. Galushin och P. Kudinov, "Scenario Grouping and Classification Methodology for Postprocessing of Data Generated by Integrated Deterministic-Probabilistic Safety Analysis," Science and Technology of Nuclear Installations, 2015.

[51]

D. Grishchenko et al., "The TALL-3D facility design and commissioning tests for validation of coupled STH and CFD codes," Nuclear Engineering and Design, vol. 290, s. 144-153, 2015.

[52]

G. Pohlner et al., "Analyses on ex-vessel debris formation and coolability in SARNET frame," Annals of Nuclear Energy, vol. 74, s. 50-57, 2014.

[53]

Y. Vorobyev et al., "Application of information technologies (genetic algorithms, neural networks, parallel calculations) in safety analysis of Nuclear Power Plants," Proceedings of the Institute for System Programming, vol. 26, no. 2, s. 137-158, 2014.

[54]

H. Li, W. Villanueva och P. Kudinov, "Approach and Development of Effective Models for Simulation of Thermal Stratification and Mixing Induced by Steam Injection into a Large Pool of Water," Science and Technology of Nuclear Installations, s. 108782, 2014.

[55]

R. Meignen et al., "Status of steam explosion understanding and modelling," Annals of Nuclear Energy, vol. 74, s. 125-133, 2014.

[56]

H. Li et al., "Validation of Effective Models for Simulation of Thermal Stratification and Mixing Induced by Steam Injection into a Large Pool of Water," Science and Technology of Nuclear Installations, s. 752597, 2014.

[57]

P. Kudinov et al., "Agglomeration and size distribution of debris in DEFOR-A experiments with Bi2O3-WO3 corium simulant melt," Nuclear Engineering and Design, vol. 263, s. 284-295, 2013.

[58]

S. E. Yakush, P. Kudinov och N. T. Lubchenko, "Coolability of heat-releasing debris bed. Part 1 : Sensitivity analysis and model calibration," Annals of Nuclear Energy, vol. 52, no. SI, s. 59-71, 2013.

[59]

S. E. Yakush, P. Kudinov och N. T. Lubchenko, "Coolability of heat-releasing debris bed. Part 2 : Uncertainty of dryout heat flux," Annals of Nuclear Energy, vol. 52, no. SI, s. 72-79, 2013.

[60]

P. Kudinov och M. Davydov, "Development and validation of conservative-mechanistic and best estimate approaches to quantifying mass fractions of agglomerated debris," Nuclear Engineering and Design, vol. 262, s. 452-461, 2013.

[61]

C. T. Tran och P. Kudinov, "The effective convectivity model for simulation of molten metal layer heat transfer in a boiling water reactor lower head," Science and Technology of Nuclear Installations, vol. 2013, s. 231501, 2013.

[62]

W. Villanueva, C. T. Tran och P. Kudinov, "Coupled thermo-mechanical creep analysis for boiling water reactor pressure vessel lower head," Nuclear Engineering and Design, vol. 249, s. 146-153, 2012.

[63]

C. T. Tran, P. Kudinov och T.-N. Dinh, "An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head," Nuclear Engineering and Design, vol. 240, no. 9, s. 2148-2159, 2010.

[64]

P. Kudinov et al., "THE DEFOR-S EXPERIMENTAL STUDY OF DEBRIS FORMATION WITH CORIUM SIMULANT MATERIALS," Nuclear Technology, vol. 170, no. 1, s. 219-230, 2010.

[65]

A. Karbojian et al., "A scoping study of debris bed formation in the DEFOR test facility," Nuclear Engineering and Design, vol. 239, no. 9, s. 1653-1659, 2009.

[66]

P. Kudinov och V. Kudinova, "Influence of Water Subcooling on Fracture of Melt Debris Particle," Transactions of the American Nuclear Society, vol. 101, no. 1, s. 543-545, 2009.

[67]

L. Dombrovsky, M. Davydov och P. Kudinov, "Thermal radiation modeling in numerical simulation of melt-coolant interaction," Computational Thermal Sciences, vol. 1, no. 1, s. 1-35, 2009.

[68]

P. Kudinov, "Comparative testing of turbulence models of Spalart-Allmaras and Menter on the problem of transsonic flow about of single aerofoil RAE 2822," Bulletin of Dnipropetrovsk National University, vol. 8, no. 1, s. 34-42, 2004.

[69]

P. Kudinov och V. Yericheva, "Численное исследование резонансных режимов аэроупругих колебаний кругового цилиндра," Bulletin of Dnipropetrovsk National University, vol. 8, no. 1, s. 43-50, 2004.

[70]

O. Prykhodko och P. Kudinov, "Численное моделирование нестационарного взаимодействия подвижных решеток профилей компрессора и трансзвуковых течений с фазовыми переходами," Aerodynamics: problems and perspectives. Kharkov: National Academy of Ukraine Kharkov Institute of Aviation, s. 93-111, 2004.

[71]

S. Isaev et al., "Numerical analysis of the jet-vortex pattern of flow in a rectangular trench," Journal of Engineering Physics and Thermophysics, vol. 76, no. 2, s. 257-265, 2003.

Konferensbidrag

[72]

K. W. Wong et al., "CFD STUDIES OF SEPARATE EFFECT FLOW ACCELERATED CORROSION AND EROSION (SEFACE) FACILITY FOR HEAVY LIQUID METAL," i Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables : United to Provide Carbon Neutral Power", ICONE 2023, 2023.

[73]

X. Wang et al., "TRANSIENT ANALYSIS OF THERMAL STRATIFICATION AND MIXING IN PRESSURE SUPPRESSION POOL DURING ANTICIPATED SCENARIOS," i Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, 2023.

[74]

S. Galushin et al., "Treatment of Phenomenological Uncertainties in Level 2 PSA for Nordic BWR Using Risk Oriented Accident Analysis Methodology," i Probabilistic Safety Assessment and Management, PSAM 2022, 2022.

[75]

X. Wang, D. Grishchenko och P. Kudinov, "Development of effective momentum model for steam injection through multi-hole spargers : Unit cell model," i Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE28), 2021.

[76]

X. Wang, D. Grishchenko och P. Kudinov, "Development of effective momentum model for steam injection through multi-hole spargers using a condensation region approach," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2020.

[77]

S. Galushin och P. Kudinov, "Comparison of vessel failure mode and melt release conditions in unmitigated and mitigated station blackout scenarios in nordic BWR using melcor code," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.

[78]

P. Kudinov et al., "Development of risk oriented accident analysis methodology (ROAAM+) for assessment of ex-vessel severe accident management effectiveness," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 2519-2535.

[79]

A. Papukchiev, D. Grishchenko och P. Kudinov, "Importance of conjugate heat transfer modeling in transient CFD simulations," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 615-626.

[80]

X. Wang et al., "Post-test calibration of the Effective Momentum Source (EMS) model for steam injection through multi-hole spargers," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 6176-6189.

[81]

X. Wang et al., "Pre-test analysis for HYMERES-2 PANDA tests series for steam injection into pool through spargers," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 6190-6203.

[82]

S. Galushin, D. Grishchenko och P. Kudinov, "Quantification of the uncertainty due to state-of-knowledge using ROAAM+ framework for Nordic BWRs," i PSA 2019 - International Topical Meeting on Probabilistic Safety Assessment and Analysis, 2019, s. 834-840.

[83]

D. Grishchenko, S. Galushin och P. Kudinov, "Risk of containment failure due to ex-vessel steam explosion for Nordic BWRs," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 4032-4038.

[84]

S. Galushin, D. Grishchenko och P. Kudinov, "Surrogate Model Development for Prediction of Vessel Failure Mode and Melt Release Conditions in Nordic BWR based on MELCOR code," i International Conference on Nuclear Engineering, Proceedings, ICONE, Volume 2019-May, 2019.

[85]

S. Galushin och P. Kudinov, "The effect of severe accident scenarios on in-vessel debris relocation in Nordic BWRs," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 1957-1970.

[86]

S. Galushin, D. Grishchenko och P. Kudinov, "The effect of vessel failure and melt release on risk of containment failure due to ex-vessel steam explosion in Nordic BWR," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.

[87]

S. Galushin och P. Kudinov, "Uncertainty analysis of vessel failure mode and melt release in station blackout scenario in Nordic BWR using MELCOR code," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 1944-1956.

[88]

D. Grishchenko och P. Kudinov, "Validation of a full model for the analysis of ex-vessel steam explosion in LWRs," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 4568-4574.

[89]

A. Papukchiev et al., "Validation of the system thermal-hydraulics code ATHlet for the simulation of transient lead-bismuth eutectic flows," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 810-822.

[90]

S. Galushin och P. Kudinov, "Analysis of the effect of severe accident scenario on the vessel lower head failure in Nordic BWR using MELCOR code," i PSAM 2018 - Probabilistic Safety Assessment and Management, 2018.

[91]

S. Galushin et al., "Joint application of risk oriented accident analysis methodology and PSA level 2 to severe accident issues in Nordic BWR," i PSAM 2018 - Probabilistic Safety Assessment and Management, 2018.

[92]

S. Galushin, P. Kudinov och D. Grishchenko, "Risk Analysis Framework for Decision Support for Severe Accident Mitigation Strategy in Nordic BWR," i PSAM 2018 - Probabilistic Safety Assessment and Management, 2018.

[93]

S. Galushin och P. Kudinov, "Sensitivity Analysis of the Vessel Lower Head Failure in Nordic BWR using MELCOR Code," i PSAM 2018 - Probabilistic Safety Assessment and Management, 2018.

[94]

D. Grishchenko et al., "Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a nordic type BWR," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017.

[95]

A. Miassoedov et al., "Results of the defor-rod1 test on the influence of BWR control rod guide tubes on melt jet fragmentation," i Transactions of the American Nuclear Society, 2017, s. 913-916.

[96]

S. Galushin, D. Grishchenko och P. Kudinov, "Risk analysis framework for severe accident mitigation strategy in nordic BWR : An approach to communication and decision making," i International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017, 2017, s. 587-594.

[97]

S. Galusin et al., "An approach to joint application of integrated deterministic-probabilistic safety analysis and PSA Level 2 to severe accident issues in Nordic BWRs," i PSAM 2016 - 13th International Conference on Probabilistic Safety Assessment and Management2017, 2016.

[98]

P. Kudinov et al., "Application of integrated deterministic-probabilistic safety analysis to assessment of severe accident management effectiveness in Nordic BWRs," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.

[99]

S. Galushin och P. Kudinov, "Comparison of melcor code versions predictions of the properties of relocated debris in lower plenum of nordic BWR," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.

[100]

S. Galusin et al., "Development of Core Relocation Surrogate Model for Prediction of Debris Properties in Lower Plenum of a Nordic BWR," i NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Gyeongju, Korea, October 9-13, 2016. Paper N11P1234, 2016.

[101]

S. Galushin och P. Kudinov, "Effect of severe accident scenario and modeling options in melcor on the properties of relocated debris in nordic BWR lower plenum," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.

[102]

S. E. Yakush och P. Kudinov, "Melt agglomeration influence on ex-vessel debris bed coolability," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.

[103]

I. Gallego-Marcos et al., "Modeling of Thermal Stratification and Mixing Induced by Steam Injection Through Spargers Into a Large Water Pool," i CFD4NRS-6, At Cambridge MA, 2016.

[104]

I. Gallego-Marcos, W. Villanueva och P. Kudinov, "Modeling of Thermal Stratification and Mixing in a Pressure Suppression Pool Using GOTHIC," i NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, At Gyeongju, Korea, 2016.

[105]

C. Journeau et al., "SAFEST ROADMAP FOR CORIUM EXPERIMENTAL RESEARCH IN EUROPE," i PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 4, 2016.

[106]

I. Gallego-Marcos, W. Villanueva och P. Kudinov, "Scaling and CFD Modelling of the Pool Experiments with Spargers Performed in the PANDA Facility," i NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, At Gyeongju, Korea, 2016.

[107]

S. Basso et al., "Validation of DECOSIM code against experiments on particle spreading by two-phase flows in water pool," i Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, NUTHOS-11, 2016.

[108]

I. Gallego-Marcos, W. Villanueva och P. Kudinov, "Water Distribution in a Nordic BWR Containment During a LOCA," i 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, 2016.

[109]

R. Kumar et al., "A PSA Level-1 method with repairable components : An application to ASTRID Decay Heat Removal systems," i Safety and Reliability : Methodology and Applications - Proceedings of the European Safety and Reliability Conference, ESREL 2014, 2015, s. 1611-1617.

[110]

C. -. Tran et al., "A study on transient heat transfer of the EU-ABWR external core catcher using the Phase-change Effective Convectivity Model," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 6821-6834.

[111]

D. Grishchenko et al., "Development of Texas-V code surrogate model for assessment of steam explosion impact in Nordic BWR," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, 2015, s. 7222-7235.

[112]

I. Mickus et al., "Development of tall-3d test matrix for APROS code validation," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 4562-4575.

[113]

A. Goronovski et al., "Effect of Corium Non-homogeneity on Nordic BWR Vessel Failure Mode and Timing," i 2015 International Congress on Advances in Nuclear Power Plants (ICAPP2015), 2015.

[114]

S. E. Yakush et al., "Effect of particle spreading on coolability of Ex-Vessel debris BED," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 1210-1222.

[115]

P. Kudinov et al., "Experimental investigation of debris bed agglomeration and particle size distribution using W03-ZR02 melt," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 8046-8054.

[116]

A. Konovalenko et al., "Experiments and modeling of particulate debris spreading in a pool," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 8055-8068.

[117]

V.-A. Phung et al., "Prediction of Corium Debris Characteristics in Lower Plenum of a Nordic BWR in Different Accident Scenarios Using MELCOR Code," i 2015 International Congress on Advances in Nuclear Power Plants, 2015.

[118]

I. Mickus, J. Lappalainen och P. Kudinov, "Validation of APROS Code Against Experimental Data from a Lead-Bismuth Eutectic Thermal-Hydraulic Loop," i Proceedings of ICAPP 2015, May 03-06, 2015 - Nice (France), 2015.

[119]

P. Kudinov et al., "A framework for assessment of severe accident management effectiveness in Nordic BWR plants," i PSAM 2014 - Probabilistic Safety Assessment and Management, 2014.

[120]

S. E. Yakush och P. Y. Kudinov, "A model for prediction of maximum post-Dryout temperature in decay-heated debris BED," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2014.

[121]

I. Mickus et al., "An Approach to Physics Based Surrogate Model Development for Application with IDPSA," i Probabilistic Safety Assessment and Management PSAM 12, June 2014, Honolulu, Hawaii, 2014.

[122]

A. Papukchiev et al., "Coupled 1D-3D Thermal-Hydraulic Simulations of a Liquid Metal Experiment Supplemented by Uncertainty and Sensitivity Analysis," i OECD/NEA & IAEA Workshop : Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation, 2014.

[123]

D. Grishchenko et al., "Design and Commissioning Tests of the TALL-3D Experimental Facility for Validation of Coupled STH and CFD Codes," i THINS 2014 International Workshop Modena, Italy, January 20-22, 2014, 2014.

[124]

S. Basso, A. Konovalenko och P. Kudinov, "Development of scalable empirical closures for self-leveling of particulate debris bed," i Proceedings of ICAPP 201, Paper 14330, 2014, s. 14330.

[125]

P. Kudinov och M. Davydov, "Development of surrogate model for prediction of corium debris agglomeration," i International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 2014, s. 1146-1155.

[126]

A. Konovalenko, S. Basso och P. Kudinov, "Experiments and Characterization of the Two-Phase Flow Driven Particulate Debris Spreading in the Pool," i NUTHOS-10, 2014, s. 1257.

[127]

P. Kudinov et al., "Investigation of Steam Explosion in Stratified Melt-Coolant Configuration," i The 10^th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), 2014, s. 1316.

[128]

I. Gallego-Marcos, W. Villanueva och P. Kudinov, "Possibility of Air Ingress into a BWR Containment during a LOCA in case of Activation of Containment Venting System," i 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS), 2014.

[129]

A. Papukchiev et al., "Prediction of Complex Thermal-Hydraulic Phenomena Supplemented by Uncertainty Analysis with Advanced Multiscale Approaches for the TALL-3D T01 Experiment," i Proceedings of the 12th International Probabilistic Safety Assessment and Management Conference (PSAM 12), 2014.

[130]

M. Jeltsov, W. Villanueva och P. Kudinov, "Risk of sloshing in the primary system of a lead cooled fast reactor," i PSAM 2014 - Probabilistic Safety Assessment and Management, 2014.

[131]

D. Grishchenko et al., "Sensitivity Study of Steam Explosion Characteristics to Uncertain Input Parameters Using TEXAS-V Code," i NUTHOS10, Paper-1293, Okinawa, Japan, 2014, 2014.

[132]

S. Basso, A. Konovalenko och P. Kudinov, "Sensitivity and uncertainty analysis for predication of particulate debris bed self-leveling in prototypic Severe Accident (SA) conditions," i Proceedings of ICAPP 2014 : Proceedings of ICAPP 2014, Paper 14329, 2014, s. 14329.

[133]

A. Hultgren et al., "Simulation of Large Scale Erosion of a Stratified Helium Layer by a Vertical Air Jet using the GOTHIC Code," i 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), 2014.

[134]

M. Jeltsov et al., "Validation of a CFD Code Star-CCM+ for Liquid Lead-Bismuth Eutectic Thermal-Hydraulics Using TALL-3D Experiment," i The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10) NUTHOS10-1269 Okinawa, Japan, December 14-18, 2014, 2014.

[135]

C. Torregrosa et al., "Coupled 3D Thermo-mechanical Analysis of a Nordic BWR Vessel Failure and Timing," i Proceedings 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), 2013.

[136]

M. Jeltsov et al., "Development of a Domain Overlapping Coupling Methodology for STH/CFD Analysis of Heavy Liquid Metal Thermal-hydraulics," i Proc. 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), 2013.

[137]

S. Yakush et al., "In-vessel Debris Bed Coolability and its Influence on the Vessel Failure," i Proc. 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), 2013.

[138]

D. Grishchenko et al., "Insight into steam explosion in stratified melt-coolant configuration," i 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2013.

[139]

L. Manickam, P. Kudinov och S. Bechta, "On the influence of subcooling and melt jet parameters on debris formation," i NURETH-15, 2013.

[140]

S. Yakush, N. Lubchenko och P. Kudinov, "Risk And Uncertainty Quantification In Debris Bed Coolability," i 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2013.

[141]

G. Bandini et al., "Safety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor," i International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), 2013.

[142]

S. Yakush, N. Lubchenko och P. Kudinov, "Surrogate Models for Debris Bed Dryout," i The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15, 2013.

[143]

A. Goronovski et al., "The Effect of Internal Pressure and Debris Bed Thermal Properties on BWR Vessel Lower Head Failure and Timing," i Proc. 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), 2013.

[144]

W. Villanueva, C. T. Tran och P. Kudinov, "Analysis of Instrumentation Guide Tube Failure in a BWR Lower Head," i Proc. 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), 2012.

[145]

A. Konovalenko och P. Kudinov, "Development of Scaling Approach for Prediction of Terminal Spread Thickness of Melt Poured into a Pool of Water," i The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), Kaohsiung, Taiwan, September 9-13, 2012, 2012.

[146]

M. Jeltsov et al., "Development of TALL-3D Facility Design for Validation of Coupled STH and CFD Codes," i Proceedings of The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), 2012.

[147]

M. Jeltsov et al., "Development of domain overlapping STH/CFD coupling approach for analysis of heavy liquid metal thermal hydraulics in TALL-3D experiment," i CFD4NRS-4, 2012.

[148]

Y. Vorobyev och P. Kudinov, "Development of methodology for identification of failure domains with GA-DPSA," i 11th International Probabilistic Safety Assessment and Management Conference and the Annual European Safety and Reliability Conference 2012, PSAM11 ESREL 2012 : Volume 3, 2012, s. 2480-2489.

[149]

M. Jeltsov et al., "Development of multi-scale simulation methodology for analysis of heavy liquid metal thermal hydraulics with coupled STH and CFD codes," i Proceedings of The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), 2012.

[150]

W. Villanueva, C.-T. Tran och P. Kudinov, "Effect Of CRGT Cooling On Modes Of Global Vessel Failure Of A BWR Lower Head," i Proceedings Of The 20th International Conference On Nuclear Engineering And The ASME 2012 Power Conference - 2012, Vol2, 2012, s. 467-477.

[151]

A. Konovalenko, A. Karbojian och P. Kudinov, "Experimental Results on Pouring and Underwater Liquid Melt Spreading and Energetic Melt-coolant Interaction," i Proceedings of The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), Kaohsiung, Taiwan, September 9-13, 2012.

[152]

A. Konovalenko et al., "Experimental and Analytical Study of the Particulate Debris Bed Self-leveling," i The 9^th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), Kaohsiung, Taiwan, September 9-13, 2012, 2012.

[153]

V.-A. Phung och P. Kudinov, "Identification of Two-Phase Flow Regimes in Unstable Natural Circulation Using TRACE and RELAP5," i Proceedings of The 9th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-9), 2012, s. N9P0062.

[154]

W. Ma et al., "Progress in melt pool behavior and coolability in the lower head of a light water reactor," i ERMSAR-2012, 2012.

[155]

S. E. Yakush, N. T. Lubchenko och P. Kudinov, "Risk-informed approach to debris bed coolability issue," i Proceedings Of The 20th International Conference On Nuclear Engineering And The ASME 2012 Power Conference - 2012, Vol 2, 2012, s. 531-543.

[156]

W. Villanueva, C. T. Tran och P. Kudinov, "A Computational Study On Instrumentation Guide Tube Failure During a Severe Accident in Boiling Water Reactor," i The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), 2011.

[157]

C. T. Tran, W. Villanueva och P. Kudinov, "A Study on the Integral Effect of Corium Material Properties on Melt Pool Heat Transfer in a Boiling Water Reactor," i Proceedings 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14), 2011.

[158]

M. Jeltsov et al., "An Approach to Validation of Coupled CFD and System Thermal-Hydraulics Codes.," i The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), 2011.

[159]

L. Li et al., "An Experimental Study on Dryout Heat Flux in Particulate Bed Packed with Irregular Particles," i Proceedings of the 2011 international congress on advances in nuclear power plants : ICAPP2011, 2011.

[160]

W. Villanueva, C. T. Tran och P. Kudinov, "Assessment with Coupled Thermo-Mechanical Creep Analysis of Combined CRGT and External Vessel Cooling Efficiency for a BWR," i The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), 2011.

[161]

Y. Vorobyev och P. Kudinov, "Development and Application of a Genetic Algorithm Based Dynamic PRA Methodology to Plant Vulnerability Search," i International Topical Meeting on Probabilistic Safety Assessment and Analysis 2011, PSA 2011, 2011, s. 559-573.

[162]

H. Li, P. Kudinov och W. Villanueva, "Development and implementation of effective models in GOTHIC for the prediction of mixing and thermal stratification in a BWR pressure suppression pool," i Proceedings of the 2011 international congress on advances in nuclear power plants : ICAPP2011, 2011.

[163]

S. Yakush och P. Kudinov, "Effects of Water Pool Subcooling on the Debris Bed Spreading by Coolant Flow," i ICAPP2011 : Proceedings of the 2011 international congress on advances in nuclear power plants, 2011.

[164]

C. T. Tran och P. Kudinov, "Local Heat Transfer From The Corium Melt Pool to the BWR Vessel Wall," i The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), 2011.

[165]

S. Yakush, P. Kudinov och N. Lubchenko, "Sensitivity and Uncertainty Analysis of Debris Bed Coolability," i The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), 2011.

[166]

M. Jeltsov och P. Kudinov, "Simulation of a Steam Bubble Transport in the Primary System of the Pool Type Lead Cooled Fast Reactors," i , 2011.

[167]

C. T. Tran och P. Kudinov, "A Synergistic use of CFD, Experiments and Effective Convectivity Model to Reduce Uncertainty in BWR Severe Accident Analysis," i CFD for Nuclear Reactor Safety Applications (CFD4NRS-3) Workshop. Washington, DC, USA. 3 September 2010, 2010.

[168]

P. Kudinov och V. Kudinova, "Cavity Formation in Particles Obtained from a High Temperature Oxidic Melt Jet Disintegration in Water," i 7th International Conference on Multiphase Flow - ICMF 2010 Proceedings, 2010, s. 11.6.2.

[169]

P. Kudinov och M. Davydov, "Development and Validation of the Approach to Prediction of Mass Fraction of Agglomerated Debris," i The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010.

[170]

W. Frid och P. Kudinov, "Ex-Vessel Melt Coolability Issue in BWRs with Deep Water Pool in Lower Drywell," i , 2010.

[171]

P. Kudinov, A. Karbojian och W. Villanueva, "Fraction of Agglomerated Debris in Experiment on Pouring of High Temperature Melt in Water," i Proc. 8th International TopicalMeeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010.

[172]

P. Kudinov, V. Kudinova och T.-N. Dinh, "Molten Oxidic Particle Fracture during Quenching in Water," i 7th International Conference on Multiphase Flow - ICMF 2010 Proceedings, 2010, s. P2.32.

[173]

P. Kudinov et al., "The DEFOR-A Experiment on Fraction of Agglomerated Debris as a Function of Water Pool Depth," i The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010.

[174]

A. Carlson, D. Lakehal och P. Kudinov, "A Multiscale Approach for Thin-Film Slug Flow," i Proceedings of the 7^th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, ExHFT-7, 2009.

[175]

H. Li och P. Kudinov, "An Approach to Simulation of Mixing in a Stratified Pool with the GOTHIC code," i Transactions of the American Nuclear Society, 2009, s. 550-551.

[176]

F. Cadinu, C. T. Tran och P. Kudinov, "Analysis of In-Vessel Coolability and Retention with Control Rod Guide Tube Cooling in Boiling Water Reactors," i NEA/SARNET2 Workshop - In-Vessel Coolability, NEA Headquarters, Issy-les-Moulineaux, France, October 12-14, 2009, 2009.

[177]

P. Kudinov och M. Davydov, "Approach to Prediction of Melt Debris Agglomeration Modes in a LWR Severe Accident," i Proceedings of ISAMM 2009 : Implementation of severe accident management measures, 2009.

[178]

F. Cadinu och P. Kudinov, "Development of a “Coupling-by-Closure” approach between CFD and System Thermal-Hydraulics Codes," i Proc. The 13^th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009.

[179]

P. Kudinov och M. Davydov, "Development of ex-vessel debris agglomeration mode map for a LWR severe accident conditions," i ICONE 17 : PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 3, 2009, s. 37-46.

[180]

P. Kudinov, A. Karbojian och C. T. Tran, "Experimental Investigation of Melt Debris Agglomeration with High Melting Temperature Simulant Materials," i Proceedings of implementation of severe accident management measures (ISAMM-2009), 2009.

[181]

S. Yakush, P. Kudinov och T.-N. Dinh, "Multiscale Simulations of Self-organization Phenomena in the Formation and Coolability of Corium Debris Bed," i Proc. The 13^th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009.

[182]

V.-A. Phung och P. Kudinov, "Relaxation Time Concept for Flow Regime Transition in Two-Phase Flow Simulations," i Transactions of the American Nuclear Society, 2009, s. 868-869.

[183]

S. Yakush och P. Kudinov, "Simulation of Ex-Vessel Debris Bed Formation and Coolability in a LWR Severe Accident," i Proceedings of ISAMM 2009 : Implementation of severe accident management measures, 2009.

[184]

C. T. Tran och P. Kudinov, "The effective convectivity model for simulation of molten metal layer heat transfer in a boiling water reactor lower head," i International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009, 2009, s. 1523-1537.

[185]

S. Yakush och P. Kudinov, "Transient Phenomena of Ex-vessel Debris Bed Formation in a LWR Severe Accident," i American Nuclear Society Transactions 2009, 2009, s. 546-547.

[186]

S. E. Yakush och P. Kudinov, "Transient phenomena of ex-vessel debris bed formation in an LWR severe accident," i Transactions of the American Nuclear Society, 2009, s. 546-547.

[187]

V.-A. Phung, P. Kudinov och M. Rohde, "Validation of RELAP5 with Sensitivity Analysis for Uncertainty Assessment for Natural Circulation Two-Phase Flow Instability," i Proceedings of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), 2009, s. 1-18.

[188]

P. Kudinov och T.-N. Dinh, "A Computational Study of Debris Bed Formation," i Transaction of American Nuclear Society 2008, 2008, s. 341-342.

[189]

F. Cadinu, T. Kozlowski och P. Kudinov, "A closure-on-demand approach to the coupling of CFD and system thermal-hydraulic codes," i The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), 2008.

[190]

C. T. Tran, P. Kudinov och T.-N. Dinh, "An approach to numerical simulation and analysis of molten corium coolability in a BWR lower head," i XCDF4NRS - Experiments and CFD Code Applications to Nuclear Reactor Safety. Grenoble, France. 10-12 September 2008, 2008.

[191]

H. Li och P. Kudinov, "An approach toward simulation and analysis of thermal stratification and mixing in a pressure suppression pool," i The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, 2008.

[192]

P. Kudinov et al., "An experimental study on debris formation with corium simulant materials," i International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2008, s. 1191-1199.

[193]

P. Kudinov et al., "An experimental study on debris formation with corium stimulant materials," i Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 2008), 2008.

[194]

S. Yakush, P. Kudinov och T.-N. Dinh, "Modeling of Two-Phase Natural Convection Flows in a Water Pool with a Decay-Heated Debris Bed," i Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 2008), 2008.

[195]

T.-N. Dinh, R. Hansson och P. Kudinov, "On Solidification Mechanism that Govern the Effect of Binary Melt Composition on Steam Explosion Energetics," i Transaction of American Nuclear Society 2008, 2008, s. 615-616.

[196]

T.-N. Dinh, R. Hansson Concilio och P. Kudinov, "On solidification mechanism that governs the effect of binary melt composition on steam explosion energetics," i Transactions of the American Nuclear Society, 2008, s. 615-616.

[197]

A. Carlson, P. Kudinov och C. Narayanan, "Prediction of Two-Phase Flow in Small Tubes : A Systematic Comparison of State-of-The-Art CMFD Codes," i 5th European Thermal-Sciences Conference (EUROTHERM), 2008.

[198]

V.-A. Phung et al., "Simulation of Two-Phase Flow Instability in CIRCUS Facility Using RELAP5," i Transactions of the American Nuclear Society : Volume 99, 2008, s. 813-814.

[199]

F. Cadinu, T. Kozlowski och P. Kudinov, "Study of algorithmic requirements for a system-to-CFD coupling strategy," i Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS), 2008.

[200]

L. Dombrovsky, M. Davydov och P. Kudinov, "Thermal radiation modeling in numerical simulation of melt-coolant interaction," i Proc. Int. Symp. Adv. Comput. Heat Transfer (CHT-08), 2008.

[201]

A. Karbojian et al., "A scoping study of debris formation in DEFOR experimental facility," i Proceedings of the 15th International Conference on Nuclear Engineering (ICONE15), 2007.

[202]

P. Kudinov et al., "A study of ex-vessel debris formation in a LWR severe accident," i Proceedings of the International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" : Societe Francaise d'Energie Nucleaire, 2007, s. 2848-2859.

[203]

P. Kudinov och T.-N. Dinh, "An analytical study of mechanisms that govern debris packing in a LWR severe accident," i Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007.

[204]

P. Kudinov och V. Yericheva, "Numerical methods for simulation of turbulent compressible flows on multi-block unstructured grids," i Proceedings of XII International Symposium “Methods of Discrete Singularities in Problems of Mathematical Physics, 2005, s. 130-134.

[205]

V. Yericheva och P. Kudinov, "Semianalytic method for investigation of aeroelastic resonant oscillations of profile in flow of viscid gas," i Proceedings of XII International Symposium “Methods of Discrete Singularities in Problems of Mathematical Physics", 2005, s. 126-130.

[206]

P. Kudinov och V. Yericheva, "Simulation of unsteady transonic flows on movable unstructured multi-block grids," i Proceedings of XV School-Seminar under leadership of academician A.I. Leontev, Vol.1., 2005.

[207]

P. Kudinov, "Validation of turbulence models for simulation of transonic flows with separation," i Transactions of XII International symposium 'Methods of discrete singularities in problems of mathematical physics' (MDOZMF-2005), 2005, s. 185-189.

[208]

A. Bulat, A. Voloshin och P. Kudinov, "Mathematical simulation of processes of heat and mass transfer at plasma ignition of coal powder," i Proceedings of V Minsk International Forum on Heat and Mass Transfer. Institute of Heat and Mass Transfer A.V. Lykova, 2004.

[209]

P. Kudinov och V. Yericheva, "Numerical simulation of heat-mass transfer in cascades of turbine’s and compressor’s profiles on unstructured grids," i Proceedings of V Minsk International Forum on Heat and Mass Transfer. Institute of Heat and Mass Transfer A.V. Lykova, 2004.

[210]

O. Prykhodko et al., "Numerical simulation of transonic gas-vapor flows with condensation," i Proceedings of V Minsk International Forum on Heat and Mass Transfer, Institute of Heat and Mass Transfer A.V. Lykova, 2004.

Icke refereegranskade

Konferensbidrag

[211]

S. Galusin och P. Kudinov, "An Approach to Grouping and Classification of Scenarios in Integrated Deterministic-Probabilistic Safety Analysis," i PSAM 2014 - Probabilistic Safety Assessment and Management, 2014.

[212]

P. Kudinov och M. Davydov, "Prediction of Mass Fraction of Agglomerated Debris in a LWR Severe Accident," i 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, (NURETH-14), September 25-30, 2011 in Toronto, Ontario, CANADA, 2011.

[213]

H. Li och P. Kudinov, "Effective Approaches to Simulation of Thermal Stratification and Mixing in a Pressure Suppression Pool," i CFD for Nuclear Reactor Safety Applications (CFD4NRS-3) Workshop. Bethesda, MD, USA. September 14-16, 2010, 2010.

Kapitel i böcker

[214]

C. Geffray et al., "Verification and validation and uncertainty quantification," i Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, : Elsevier, 2018, s. 383-405.

[215]

R. Kumar et al., "A PSA Level-1 method with repairable components : An application to ASTRID Decay Heat Removal systems," i Safety and Reliability: Methodology and Applications, : CRC Press, 2014, s. 1611-1617.

Rapporter

[216]

D. Grishchenko, I. Mickus och P. Kudinov, "Experimental activities report on TALL-3D," , 2015.

[217]

L. Hua, W. Villanueva och P. Kudinov, "Validation of Effective Momentum and Heat Flux Models for Stratification and Mixing in a Water Pool," , Nordic Nuclear Safety Research (NKS-Pool) Research Report, 2013.

[218]

H. Li, W. Villanueva och P. Kudinov, "Effective Models for Prediction of Stratification and Mixing Phenomena in a BWR Supression Pool," , Nordic Nuclear Reactor Thermal-Hydraulics Network (NORTHNET) Roadmap 3 Research Report, 2012.

[219]

H. Li, W. Villanueva och P. Kudinov, "Effective Momentum and Heat Flux Models for Simulation of Stratification and Mixing in a Large Pool of Water," , Nordic Nuclear Safety Research (NKS-Pool) Research Report, NKS-266, 2012.

[220]

H. Li, P. Kudinov och W. Villanueva, "Development and Validation of Effective Models for Simulation of Stratification and Mixing Phenomena in a Pool of Water," , Nordic Nuclear Safety Research (NKS-Pool) Research Report, 2011.

[221]

H. Li, P. Kudinov och W. Villanueva, "Condensation, Stratification and Mixing in aBWR Supression Pool," , Nordic Nuclear Reactor Thermal-Hydraulics Network (NORTHNET) Roadmap 3 Research report, 2010.

[222]

H. Li, P. Kudinov och W. Villanueva, "Modeling of Condensation,Stratification, and Mixing Phenomena in a Pool of Water," Nordic nuclear safety research (NKS), 2010.

[223]

H. Li och P. Kudinov, "GOTHIC code simulation of thermal stratification in POOLEX facility," , 2009.