Publications by Dmitry Grishchenko

Peer reviewed

Articles

[1]

X. Wang, D. Grishchenko and 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, pp. 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, D. Grishchenko and 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, pp. 111773, 2022.

[5]

X. Wang, D. Grishchenko and 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.

[6]

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

[7]

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

[9]

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

[10]

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

[11]

D. Grishchenko, S. Galushin and 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, pp. 63-75, 2019.

[12]

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

[13]

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

[14]

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

[15]

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

[16]

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, pp. 461-476, 2018.

[17]

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, pp. 1064-1072, 2017.

[18]

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

[19]

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, pp. 182-197, 2017.

[20]

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

[21]

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, pp. 359-370, 2016.

[22]

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

[23]

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

[24]

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, pp. 1-14, 2015.

[25]

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, pp. 144-153, 2015.

[26]

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

[27]

D. Grishchenko and 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, pp. 127-149, 2011.

[28]

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

[29]

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

Conference papers

[30]

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

[31]

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

[32]

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

[33]

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

[34]

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

[35]

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

[36]

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

[37]

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

[38]

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

[39]

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

[40]

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

[41]

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

[42]

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

[43]

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

[44]

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

[45]

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

[46]

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

[47]

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

[48]

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

[49]

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

[50]

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

[51]

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

[52]

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

[53]

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

[54]

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

[55]

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

[56]

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

[57]

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

[58]

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

[59]

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

[60]

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

[61]

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

[62]

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

[63]

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

[64]

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

[65]

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

[66]

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

[67]

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

[68]

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

Non-peer reviewed

Chapters in books

[69]

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