Publikationer av Sevostian Bechta
Refereegranskade
Artiklar
[1]
Y. Deng et al., "An experimental study on the effect of coolant salinity on steam explosion," Annals of Nuclear Energy, vol. 201, 2024.
[2]
N. Zhao, W. Ma och S. Bechta, "A review of the assessment of severe accident management guidelines and actions through analytical simulations," Annals of Nuclear Energy, vol. 180, s. 109448, 2023.
[3]
N. Zhao et al., "Assessment of safety injection in severe accident management following BDBA scenarios in a Swedish PWR," Annals of Nuclear Energy, vol. 183, 2023.
[4]
J. Stuckert et al., "Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle," Nuclear Engineering and Design, vol. 410, 2023.
[5]
L. Zhao, W. Ma och S. Bechta, "Numerical study on melt underwater spreading with MPS method," Annals of Nuclear Energy, vol. 181, s. 109581, 2023.
[6]
Y. Xiang et al., "Pre-test simulation and a scoping test for dryout and remelting phenomena of an in-vessel debris bed," Nuclear Engineering and Design, vol. 403, 2023.
[7]
L. Zhao et al., "Simulation of melt spreading over dry substrates with the moving particle Semi-implicit method," Nuclear Engineering and Design, vol. 405, no. 10, s. 112229-112229, 2023.
[8]
N. Zhao, W. Ma och S. Bechta, "Analysis of primary side bleed and feed actions for severe accident management following total loss of feed water in a Swedish PWR," Annals of Nuclear Energy, vol. 167, s. 108859-108859, 2022.
[9]
W. Villanueva et al., "Experimental investigation of melt infiltration and solidification in a pre-heated particle bed," Physics of fluids, vol. 34, no. 12, 2022.
[10]
S. Thakre et al., "Metallic melt jet fragmentation in a water pool : Experiments and numerical simulations," Nuclear Engineering and Design, vol. 396, s. 111876, 2022.
[11]
N. Zhao, W. Ma och S. Bechta, "Numerical assessment for entry condition of severe accident management guidelines in a Swedish nuclear power plant," Annals of Nuclear Energy, vol. 169, s. 108969-108969, 2022.
[12]
N. Zhao et al., "Sensitivity study of thermal-hydraulic nodalization for MELCOR simulations of severe accidents in a pressurized water reactor," Annals of Nuclear Energy, vol. 166, 2022.
[13]
N. Zhao et al., "A nodal sensitivity study of MELCOR simulation for severe accidents in a pressurized water reactor," Annals of Nuclear Energy, vol. 160, 2021.
[14]
Y. Xiang et al., "A scoping study on debris bed formation from metallic melt coolant interactions," Nuclear Engineering and Design, vol. 385, 2021.
[15]
S. M. Hoseyni et al., "Melt infiltration through porous debris at temperatures above Solidification : Validation of analytical model," Annals of Nuclear Energy, vol. 161, s. 108435, 2021.
[16]
S. M. Hoseyni et al., "Metallic melt infiltration in preheated debris bed and the effect of solidification," Nuclear Engineering and Design, vol. 379, s. 111229, 2021.
[17]
S. V. R. Bandaru et al., "Multi-nozzle spray cooling of a reactor pressure vessel steel plate for the application of ex-vessel cooling," Nuclear Engineering and Design, vol. 375, 2021.
[18]
H. Wang et al., "Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention," Nuclear Engineering and Design, vol. 379, s. 111196, 2021.
[19]
C. Journeau et al., "Transient interactions of boron carbide with molten uranium oxide," Nuclear Materials and Energy, vol. 29, 2021.
[20]
L. E. Herranz et al., "The working group on the analysis and management of accidents (WGAMA) : A historical review of major contributions," Progress in nuclear energy (New series), vol. 127, 2020.
[21]
S. V. R. Bandaru et al., "Upward-facing multi-nozzle spray cooling experiments for external cooling of reactor pressure vessels," International Journal of Heat and Mass Transfer, vol. 163, 2020.
[22]
Y. Chen et al., "A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor," Nuclear Engineering and Design, vol. 343, s. 22-37, 2019.
[23]
L. Manickam et al., "An experimental study on the intense intense heat transfer and phase change during melt and water interactions," Experimental heat transfer, vol. 32, no. 3, s. 251-266, 2019.
[24]
A. Hotta et al., "Experimental and Analytical Investigation of Formation and Cooling Phenomena in High Temperature Debris Bed," Journal of Nuclear Science and Technology, 2019.
[25]
S. Bechta et al., "On the EU-Japan roadmap for experimental research on corium behavior," Annals of Nuclear Energy, vol. 124, s. 541-547, 2019.
[26]
L. Manickam et al., "Oxidation of molten zirconium droplets in water," Nuclear Engineering and Design, vol. 354, 2019.
[27]
P. Yu et al., "Validation of a thermo-fluid-structure coupling approach for RPV creep failure analysis against FOREVER-EC2 experiment," Annals of Nuclear Energy, vol. 133, s. 637-648, 2019.
[28]
V. B. Khabensky et al., "Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention," Nuclear Engineering and Design, vol. 327, s. 82-91, 2018.
[29]
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.
[30]
F. Fichot et al., "Some considerations to improve the methodology to assess In-Vessel Retention strategy for high-power reactors," Annals of Nuclear Energy, vol. 119, s. 36-45, 2018.
[31]
J. A. Zambaux et al., "Study on thermal fragmentation characteristics of a superheated alumina droplet," Annals of Nuclear Energy, vol. 119, s. 352-361, 2018.
[32]
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.
[33]
L. Manickam, S. Bechta och W. Ma, "On the fragmentation characteristics of melt jets quenched in water," International Journal of Multiphase Flow, vol. 91, s. 262-275, 2017.
[34]
M. Fischer et al., "Core Melt Stabilization Concepts for Existing and Future LWRs and Associated Research and Development Needs," NUCLEAR TECHNOLOGY, vol. 196, no. 3, s. 524-537, 2016.
[35]
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.
[36]
V. I. Almyashev et al., "Oxidation effects during corium melt in-vessel retention," Nuclear Engineering and Design, vol. 305, s. 389-399, 2016.
[37]
B. R. Sehgal och S. Bechta, "Severe accident progression in the BWR lower plenum and the modes of vessel failure," Annals of Nuclear Energy, 2016.
[38]
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.
[39]
W. Klein-Hessling et al., "Conclusions on severe accident research priorities," Annals of Nuclear Energy, vol. 74, s. 4-11, 2014.
[40]
V. S. Granovsky et al., "Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention," Nuclear Engineering and Design, vol. 278, s. 310-316, 2014.
[41]
S. Bakardjieva et al., "Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2," Annals of Nuclear Energy, vol. 74, s. 110-124, 2014.
[42]
D. Bottomley et al., "Severe accident research in the core degradation area : An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center," Nuclear Engineering and Design, vol. 252, s. 226-241, 2012.
[43]
V. Almjashev et al., "Ternary eutectics in the systems FeO-UO2-ZrO2 and Fe2O3-U3O8-ZrO21," Radiochemistry, vol. 53, no. 1, s. 13-18, 2011.
[44]
S. Bechta et al., "INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL," Nuclear Technology, vol. 170, no. 1, s. 210-218, 2010.
[45]
S. Bakardjieva et al., "Improvement of the European thermodynamic database NUCLEA," Progress in nuclear energy (New series), vol. 52, no. 1, s. 84-96, 2010.
[46]
S. Bechta et al., "Influence of corium oxidation on fission product release from molten pool," Nuclear Engineering and Design, vol. 240, no. 5, s. 1229-1241, 2010.
[47]
V. Almjashev et al., "Phase equilibria in the FeO(1+x)-UO(2)-ZrO(2) system in the FeO(1+x)-enriched domain," Journal of Nuclear Materials, vol. 400, no. 2, s. 119-126, 2010.
[48]
V. Almjashev et al., "Eutectic crystallization in the FeO(1.5)-UO(2+x)-ZrO(2) system," Journal of Nuclear Materials, vol. 389, no. 1, s. 52-56, 2009.
[49]
V. Khabensky et al., "Severe accident management concept of the VVER-1000 and the justification of corium retention in a crucible-type core catcher," Nuclear Engineering and Technology, vol. 41, no. 5, s. 561-574, 2009.
[50]
S. Bechta et al., "VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere," Nuclear Engineering and Design, vol. 239, no. 6, s. 1103-1112, 2009.
[51]
S. Bechta et al., "Corium phase equilibria based on MASCA, METCOR and CORPHAD results," Nuclear Engineering and Design, vol. 238, no. 10, s. 2761-2771, 2008.
[52]
V. Gusarov et al., "Interaction of a material based on aluminum and iron oxides with a metal melt," Russian journal of applied chemistry, vol. 80, no. 4, s. 528-535, 2007.
[53]
S. Bechta et al., "Phase diagram of the UO2-FeO1+x system," Journal of Nuclear Materials, vol. 362, no. 1, s. 46-52, 2007.
[54]
S. Bechta et al., "Phase transformation in the binary section of the UO2-FeO-Fe system," Radiochemistry (New York, N.Y.), vol. 49, no. 1, s. 20-24, 2007.
[55]
V. Gusarov et al., "Physicochemical simulation of the combustion of materials with the total endothermal effect," Glass Physics and Chemistry, vol. 33, no. 5, s. 492-497, 2007.
[56]
V. Asmolov et al., "The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor," High Temperature, vol. 45, no. 1, s. 22-31, 2007.
[57]
S. Bechta et al., "Corrosion of vessel steel during its interaction with molten corium : Part 2. Model development," Nuclear Engineering and Design, vol. 236, no. 13, s. 1362-1370, 2006.
[58]
S. Bechta et al., "Corrosion of vessel steel during its interaction with molten corium : Part 1. Experimental," Nuclear Engineering and Design, vol. 236, no. 17, s. 1810-1829, 2006.
[59]
V. Gusarov et al., "Distribution of components between immiscible melts of a system under nonisothermal conditions," Glass Physics and Chemistry, vol. 32, no. 6, s. 638-642, 2006.
[60]
S. Bechta et al., "Phase Relations in the ZrO2–FeO System," Russian Journal of Inorganic Chemistry, vol. 51, no. 2, s. 325-331, 2006.
[61]
L. Mezentseva et al., "Phase and chemical transformations in the SiO2-Fe2O3(Fe3O4) system at various oxygen partial pressures," Russian Journal of Inorganic Chemistry, vol. 51, no. 1, s. 118-125, 2006.
[62]
S. Bechta et al., "Phase diagram of the ZrO2-FeO system," Journal of Nuclear Materials, vol. 348, no. 1-2, s. 114-121, 2006.
[63]
V. Gusarov et al., "Physicochemical Modeling and Analysis of the Interaction between a Core Melt of the Nuclear Reactor and a Sacrificial Material," Glass Physics and Chemistry, vol. 31, no. 1, s. 53-66, 2005.
[64]
V. Gusarov et al., "Новый класс функциональных материалов для устройства локализации расплава активной зоны ядерного реактора," Russian chemical journal, vol. 49, no. 4, s. 42-53, 2005.
[65]
S. Bechta et al., "Experimental studies of oxidic molten corium-vessel steel interaction," Nuclear Engineering and Design, vol. 210, no. 1-3, s. 193-224, 2001.
[66]
S. Bechta et al., "Water boiling on the corium melt surface under VVER severe accident conditions," Nuclear Engineering and Design, vol. 195, no. 1, s. 45-56, 2000.
Konferensbidrag
[67]
L. Zhao et al., "Modelling of corium dry spreading with MPS method," i The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022.
[68]
Y. Xiang et al., "Pre-test simulations and a scoping test for dryout and remelting phenomena of an in-vessel debris beds," i The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022.
[69]
Q. Guo et al., "Effects of salinity in coolant on steam explosion," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 4556-4567.
[70]
F. Fichot et al., "A revised methodology to assess in-vessel retention strategy for high-power reactors," i PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 18, VOL 7, 2018.
[71]
P. Yu et al., "Coupled Thermo-Mechanical Creep Analysis For A Nordic BWR Lower Head Using Non-Homogeneous Debris Bed Configuration From MELCOR," i 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.
[72]
D. B. Lopukh et al., "Numerical Simulation of Induction Heating for Molten Pool heat Transfer Experiments in Slice Geometry," i 2018 INTERNATIONAL SCIENTIFIC MULTI-CONFERENCE ON INDUSTRIAL ENGINEERING AND MODERN TECHNOLOGIES (FAREASTCON), 2018.
[73]
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.
[74]
P. Yu et al., "Pre-Test Simulations of SIMECO-2 Experiments on Stratified Melt Pool Heat Transfer," i The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), 2016.
[75]
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.
[76]
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.
[77]
M. Fischer et al., "Core melt stabilization concepts for existing and future LWRs and associated R&D needs," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 7578-7592.
[78]
P. Dietrich et al., "Coupling of melcor with the pecm for improved modelling of a core melt in the lower plenum," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2015.
[79]
P. Dietrich et al., "Extension of the MELCOR code for analysis of late in-vessel phase of a severe accident," i IYCE 2015 - Proceedings : 2015 5th International Youth Conference on Energy, 2015.
[80]
A. Mlassoedov et al., "Severe accident facilities for European safety targets : The safest project," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 4604-4616.
[81]
B. R. Sehgal och S. Bechta, "Severe accident progression in the BWR lower plenum and the modes of vessel failure," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 8035-8045.
[82]
P. Kudinov et al., "Investigation of Steam Explosion in Stratified Melt-Coolant Configuration," i The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10), 2014, s. 1316.
[83]
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.
[84]
D. Grishchenko et al., "Insight into steam explosion in stratified melt-coolant configuration," i 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2013.
[85]
L. Manickam, P. Kudinov och S. Bechta, "On the influence of subcooling and melt jet parameters on debris formation," i NURETH-15, 2013.
[86]
V. S. Granovsky et al., "Modeling of melt retention in EU-APR1400 ex-vessel core catcher," i International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, 2012, s. 1412-1421.
[87]
S. Bechta et al., "Influence of corium oxidation on fission product release from molten pool," i Proceedings of 2009 International Congress on Advances in Nuclear Power Plants : ICAPP 2009, 2009.
[88]
S. Bechta et al., "Interaction between molten corium UO2+X-ZrO2-FeO y and VVER vessel steel," i Proceeding of International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2009, s. 210-218.
[89]
V. Vasilenko et al., "NITI severe accident research under ISTC coordination," i Proceedings of FISA 2009, Seventh European Commission conference on Euratom research and training in reactor systems, 2009.
[90]
S. Bechta et al., "Prospects of application of quantitative x-ray fluorescence analysis in nuclear industry : Existing solutions and new approaches," i Proceeding of the 5th interindustrial meeting “Problems and developments of chemical and radiochemical monitoring in atomic energy”, 2009.
[91]
S. Bakardjieva et al., "Improvement of the European thermodynamic database NUCLEA in the frame of EU-funded experiments," i Proceedings of the 3rd European Review Meeting on Severe Accident Research (ERMSAR 2008), 2008.
[92]
S. Bechta et al., "VVER steel corrosion during in-vessel retention of corium melt," i Proceedings of the 3rd European Review Meeting on Severe Accident Research (ERMSAR 2008), 2008.
[93]
S. Smirnov, V. Granovsky och S. Bechta, "DNS of Molten Corium Pool Inductively Heated in a Cold Crucible," i Proceedings of the MASCA2 Seminar 2007, 2007.
[94]
V. Gusarov, V. Almjashev och S. Bechta, "Influence of the Temperature Difference at Immiscibility Liquids Interface on their Phase Instability," i Proceedings of the MASCA2 Seminar 2007, 2007.
[95]
V. Asmolov, D. Tsurikov och S. Bechta, "Molten Corium Stratification and Component Partitioning," i Proceedings of the MASCA2 Seminar 2007, 2007.
[96]
S. Bechta et al., "Experimental study of interactions between suboxidized corium and reactor vessel steel," i Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, 2006, s. 1355-1362.
[97]
S. Bechta, V. Khabensky och V. Granovsky, "ISTC CORPHAD Project : Experimental study of corium phase diagram," i Proceedings of International Information Exchange Meeting on Thermodynamics of Nuclear Fuels, 2006.
[98]
S. Bechta et al., "CORPHAD and METCOR ISTC projects," i Proceedings of The first European Review Meeting on Severe Accident Research (ERMSAR-2005), 2005.
[99]
V. Asmolov et al., "Crucible-type core catcher for VVER-1000 reactor," i Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, 2005, s. 1221-1227.
[100]
A. Sulatsky et al., "Molten corium interaction with oxidic sacrificial material of WER core catcher," i Proceedings of the American Nuclear Society : International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, 2005, s. 1238-1246.
[101]
S. Bechta, V. Granovsky och A. Sulatsky, "Model of Interaction of Molten Steel with Sacrificial Material of VVER Core Catcher," i Proceedings of Research Workshop “Evaluation of experimental data and verification of computer codes", 2004.
[102]
S. Bechta et al., "New experimental results on the interaction of molten corium with reactor vessel steel," i Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, 2004, s. 1072-1081.
[103]
V. Asmolov et al., "Partitioning of Zr, U and FP between Molten Oxidic and Metallic Corium," i Proceeding of MASCA Seminar, 2004.
Böcker
[104]
D. Lopukh et al., Inductional melting of corium and glass in cold crucible. Properties and modelling. St Petersburg : St. Petersburg Electro-technical University LETI, 2021.
[105]
D. Lopukh et al., Индукционная плавка кориума в холодном тигле : Оборудование и применение. St Petersburg : St. Petersburg Electro-technical University LETI, 2019.
[106]
V. Asmolov et al., RASPLAV: Retention of molten core materials of water cooled reactors : OECD RASPLAV and MASCA Projects (1994-2006)Edited by V.G. Asmolov, A.Yu. Rumiantsev and V.F. Strizhov. Moscow : ROSENERGOATOM, 2018.
Icke refereegranskade
Artiklar
[107]
H. Y. Kim et al., "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor," Science and Technology of Nuclear Installations, 2018.
Konferensbidrag
[108]
V. Khabensky, S. Bechta och V. Gusarov, "MASCA, METCOR and CORPHAD Results and Corium Phase Equilibrium," i Proceedings of the MASCA2 Seminar 2007, 2007.
Kapitel i böcker
[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, : CRC Press, 2014, s. 1611-1617.
Proceedings (redaktörskap)
[110]
"Improvement of the European thermodynamic database NUCLEA in the frame of EU-funded experiments," , Proceedings of Conference on Systems Engineering Research, 2012.
Patent
Patent
[111]
[112]
[113]
[114]
V. Khabensky, V. Granovsky och S. Bechta, "Devise for localization and cooling of corium of accidental light water nuclear reactor," ru 35463, 2003.
[115]
V. Khabensky, V. Granovsky och S. Bechta, "System for localization and cooling of corium of accidental light water nuclear reactor," ru 2253914-C2 (2005-06-10), 2003.
[116]
V. Gusarov et al., "Method for producing ceramic materials incorporating ferric oxide, alumina, and silicon dioxide for nuclear-reactor molten core trap," ru 2206930-C1 (2003-06-20), 2002.
[117]
V. Gusarov et al., "Oxide material for a molten core catcher of a nuclear reactor," ru 2178924 (2002-01-27), 2001.
[118]
V. Gusarov et al., "Oxidic material for nuclear reactor core melt catcher," ru 2191436 (2002-11-20), 2001.
[119]
V. Gusarov et al., "Oxidic material for nuclear reactor core melt catcher," ru 2192053 (2002-10-27), 2001.
[120]
V. Gusarov et al., "Oxidmaterial for fallan av en karnreaktors smalt mantel," fi 118445 (2007-11-15), 2001.
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