Publikationer av Dmitry Grishchenko

Refereegranskade

Artiklar

[1]

X. Wang, D. Grishchenko och P. Kudinov, "Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers," Nuclear engineering and technology : an international journal of the Korean Nuclear Society, vol. 56, no. 3, s. 1052-1065, 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 et al., "Momentum induced by steam injection into a subcooled pool," International Journal of Heat and Mass Transfer, vol. 232, 2024.

[4]

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.

[5]

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.

[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]

V. H. Sanchez-Espinoza et al., "The H2020 McSAFER Project : Main Goals, Technical Work Program, and Status," Energies, vol. 14, no. 19, 2021.

[8]

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.

[9]

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.

[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]

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

[12]

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.

[13]

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

[14]

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.

[15]

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.

[16]

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.

[17]

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.

[18]

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.

[19]

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.

[20]

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.

[21]

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.

[22]

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.

[23]

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.

[24]

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.

[25]

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.

[26]

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.

[27]

Y. Udalov et al., "Coordination Nature of Phase Separation in Oxide Melts," Glass Physics and Chemistry, vol. 39, no. 4, s. 431-443, 2013.

[28]

D. Grishchenko och P. Piluso, "Recent progress in the gas-film levitation as a method for thermophysical properties measurements : application to ZrO₂-Al₂O₃system," High Temperatures-High Pressures, vol. 40, no. 2, s. 127-149, 2011.

[29]

Yu. P. Udalo et al., "Phase Separation in Melts of the ZrO2–Al2O3 System," Glass Physics and Chemistry, vol. 34, no. 5, s. 623-633, 2008.

[30]

Yu. P. Udalov et al., "Monotectic Crystallization of Melts in the ZrO2–Al2O3 System," Glass Physics and Chemistry, vol. 32, no. 4, s. 479-485, 2006.

Konferensbidrag

[31]

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.

[32]

G. Acharya et al., "Source Term Uncertainty Analysis of Severe Accidents in Nordic BWRs," i Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, 2023, s. 4137-4150.

[33]

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.

[34]

H. Suikkanen et al., "Thermal Hydraulic Experiments and Code Validation for LWR SMRs within the European McSAFER Project : Overview of Activities and Current Status," i Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, 2023, s. 2388-2401.

[35]

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.

[36]

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.

[37]

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.

[38]

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.

[39]

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.

[40]

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.

[41]

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.

[42]

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.

[43]

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.

[44]

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.

[45]

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.

[46]

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.

[47]

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.

[48]

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.

[49]

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.

[50]

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.

[51]

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.

[52]

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.

[53]

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.

[54]

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.

[55]

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.

[56]

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.

[57]

A. Papukchiev et al., "Multiscale analysis of forced and natural convection including heat transfer phenomena in the tall-3D experimental facility," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, 2015, s. 2917-2930.

[58]

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.

[59]

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.

[60]

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.

[61]

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.

[62]

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.

[63]

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.

[64]

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

[65]

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.

[66]

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.

[67]

M. Zabiego et al., "The KROTOS KFC and SERENA/KS1 tests : experimental results and MC3D calculations," i 7th International Conference on Multiphase Flow ICMF 2010, 2010.

[68]

D. Grishchenko, Yu. P. Udalov och P. PILUSO, "Thermophysical properties measurements of melts by gas-film levitation," i Collected papers of Russian Scientific and Technical conference “Electrothermy – 2008”, 2008, s. 108-117.

[69]

D. Grishchenko, "Design of the measurement cell and method of measurement of electro-physical properties in Galahov furnace," i Collected papers of Russian Scientific and Technical conference “Electrothermy – 2006”, 2006, s. 110-121.

[70]

Yu. P. Udalov och D. Grishchenko, "Liquation in melts of oxide systems," i Collected papers of Russian Scientific and Technical conference “Electrothermy – 2006”, 2006, s. 29-51.

[71]

D. Grishchenko och Yu. P. Udalov, "Structural premises of liquation in oxide melts," i Collected papers of Russian Scientific and Technical conference “Electrothermy – 2004”, 2004, s. 321-329.

Icke refereegranskade

Kapitel i böcker

[72]

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.