Publikationer av Weimin Ma
Refereegranskade
Artiklar
[1]
W. Wang och W. Ma, "Coupling of MELCOR with surrogate model for quench estimation of conical debris beds," Annals of Nuclear Energy, vol. 211, 2025.
[2]
P. Guo et al., "Evaluating uncertainties: Heat transfer parameter effects on stratified melt pool simulation," Annals of Nuclear Energy, vol. 211, 2025.
[3]
P. Guo et al., "SAMPO-P : A prototypical scale low-temperature experiment on two-layer melt pool heat transfer in LWR lower head," Experimental Thermal and Fluid Science, vol. 160, 2025.
[4]
Y. Xiang et al., "A numerical study on melt jet breakup in a water pool using coupled VOF and level set method," Nuclear Engineering and Design, vol. 426, 2024.
[5]
L. Yu et al., "A numerical study on metallic melt infiltration in porous media and the effect of solidification," Nuclear Engineering and Design, vol. 430, 2024.
[6]
D. Fang et al., "A numerical study on multi-nozzle spray cooling of downward-facing heater surface," Progress in nuclear energy (New series), vol. 173, 2024.
[7]
Y. Xiang et al., "A scoping investigation on debris bed formation with high-temperature melt simulant Fe-Sn," Applied Thermal Engineering, vol. 257, 2024.
[8]
Y. Deng et al., "An Experimental study on steam explosion of multiple droplets in different chemical solutions," International Journal of Heat and Mass Transfer, vol. 226, 2024.
[9]
Y. Deng et al., "An experimental study on the effect of chemical additives in coolant on steam explosion," International Journal of Heat and Mass Transfer, vol. 218, 2024.
[10]
Y. Deng et al., "An experimental study on the effect of coolant salinity on steam explosion," Annals of Nuclear Energy, vol. 201, 2024.
[11]
L. Yu et al., "An experimental study on the impact of particle surface wettability on melt infiltration in particulate beds," Annals of Nuclear Energy, vol. 206, 2024.
[12]
L. Zhao et al., "Application of moving particle semi-implicit method on simulating melt spreading within OECD/ROSAU project," Nuclear Engineering and Design, vol. 427, 2024.
[13]
S. Dong et al., "Critical heat flux characteristics for subcooled flow boiling on an inclined downward-heating surface in a divergent channel," Applied Thermal Engineering, vol. 255, 2024.
[14]
D. Fang et al., "Experimental and numerical studies on spray cooling of a downward-facing surface under partial coverage of multi-nozzle sprays," Nuclear Engineering and Design, vol. 428, 2024.
[15]
P. Yu et al., "Numerical investigation on the formation of focusing effect in the IVR strategy," Progress in nuclear energy (New series), vol. 177, 2024.
[16]
B. Zhang et al., "Numerical simulation for pressure fluctuations caused by the growth of a single boiling bubble," Applied Thermal Engineering, vol. 254, 2024.
[17]
L. Zhao, Y. Xiang och W. Ma, "Numerical simulation of melt penetration in debris beds using MPS method," Progress in nuclear energy (New series), vol. 167, 2024.
[18]
Q. Guo et al., "Oxidation of molten zirconium-containing droplet in water," Progress in nuclear energy (New series), vol. 175, 2024.
[19]
Y. Gong et al., "Thermophysical properties of UO2-ZrO2 melt measured by aerodynamic levitation," Journal of Nuclear Materials, vol. 602, 2024.
[20]
D. Fang et al., "A numerical study of liquid film dynamics in multi-nozzle spray cooling of downward-facing surface," International Journal of Multiphase Flow, vol. 161, 2023.
[21]
Y. Deng et al., "A numerical study on the levitation system for droplet preparation in a fuel-coolant interaction experiment," Progress in nuclear energy (New series), vol. 159, 2023.
[22]
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.
[23]
X. Zeng et al., "A scoping study on remelting process of a debris bed in the lower head of reactor pressure vessel," Annals of Nuclear Energy, vol. 189, 2023.
[24]
P. Yu et al., "An assessment of the lumped parameter model for the two-layer melt pool heat transfer," Annals of Nuclear Energy, vol. 180, 2023.
[25]
Y. Xiang et al., "An experimental investigation on debris bed formation from fuel coolant interactions of metallic and oxidic melts," Applied Thermal Engineering, vol. 233, 2023.
[26]
Y. Deng et al., "An experimental study on droplet quench and steam explosion in boric acid solutions," Progress in nuclear energy (New series), vol. 166, 2023.
[27]
Q. Guo, Y. Deng och W. Ma, "An experimental study on quenching of metallic spheres in seawater," Experimental Thermal and Fluid Science, vol. 148, 2023.
[28]
W. Wang och W. Ma, "Application of deterministic sampling methods to uncertainty quantification in MELCOR severe accident simulation," Nuclear Engineering and Design, vol. 403, 2023.
[29]
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.
[30]
W. Wang och W. Ma, "Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident," Progress in nuclear energy (New series), vol. 157, 2023.
[31]
W. Wang och W. Ma, "Deterministic sampling methods coupled with dynamic coverage factors for uncertainty analyses in MELCOR simulation," Nuclear Engineering and Design, vol. 413, 2023.
[32]
W. Wang, Y. Chen och W. Ma, "Development of a surrogate model for quenching estimation of ex-vessel debris beds and its coupling with MELCOR," Annals of Nuclear Energy, vol. 190, s. 109883, 2023.
[33]
Y. Xiang et al., "Experimental investigation on debris bed formation from metallic melt coolant interactions," International journal of thermal sciences, vol. 192, s. 108398, 2023.
[34]
Y. Xiang et al., "Experimental investigation on ex-vessel debris bed formation using low melting-point melt of binary metals," Progress in nuclear energy (New series), vol. 157, 2023.
[35]
H. Zhang et al., "Modeling and simulation of a micro gas-cooled nuclear reactor using Modelica," Frontiers in Energy Research, vol. 11, 2023.
[36]
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.
[37]
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.
[38]
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.
[39]
S. Dong et al., "Theoretical model for subcooled upward flow boiling heat transfer and critical heat flux for an inclined downward heated surface," International Journal of Heat and Mass Transfer, vol. 213, 2023.
[40]
Y. Gong et al., "Viscosity measurement of molten alumina and zirconia using aerodynamic levitation, laser heating and droplet oscillation techniques," Heliyon, vol. 9, no. 12, 2023.
[41]
P. Yu et al., "A numerical study of heat transfer in bottom-heated and side/top-cooled liquid metal layers with different aspect ratios," Annals of Nuclear Energy, vol. 177, s. 109328, 2022.
[42]
J. Min et al., "An experimental study on steam explosion of a small melt jet falling into a water pool," Nuclear Engineering and Design, vol. 391, 2022.
[43]
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.
[44]
W. Wang, Y. Chen och W. Ma, "Application of uncertainty analysis methods to MELCOR simulation of postulated severe accidents in a Nordic BWR," Nuclear Engineering and Design, vol. 392, 2022.
[45]
Y. Chen, H. Zhang och W. Ma, "Coupled MELCOR/COCOMO analysis on quench of ex-vessel debris beds," Annals of Nuclear Energy, vol. 165, 2022.
[46]
Y. Gong et al., "Density Measurement of Molten Drop With Aerodynamic Levitation and Laser Heating," Frontiers in Energy Research, vol. 10, 2022.
[47]
Z. Zhang et al., "Experimental and numerical studies on the two-dimensional flow characteristics in the radially stratified porous bed," International Communications in Heat and Mass Transfer, vol. 133, s. 105940, 2022.
[48]
X. Li et al., "Flow Pattern Identification of Porous Media Based on Signal Feature Extraction and SVM," Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics, vol. 43, no. 11, s. 2957-2965, 2022.
[49]
X. Li et al., "Identification of two-phase flow pattern in porous media based on signal feature extraction," Flow Measurement and Instrumentation, vol. 83, 2022.
[50]
Z. Zhang et al., "Investigation on Flow Characteristics in Radial Stratified Debris Bed," Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, vol. 56, no. 10, s. 2032-2040, 2022.
[51]
S. Dong et al., "Mechanistic critical heat flux model development for subcooled flow boiling based on superheated liquid sublayer depletion," Progress in nuclear energy (New series), vol. 153, s. 104445, 2022.
[52]
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.
[53]
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.
[54]
L. Zhang et al., "Numerical simulation of natural convection and heat transfer in a molten pool with embedded cooling tubes," Frontiers in Energy Research, vol. 10, 2022.
[55]
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.
[56]
L. Zhang et al., "Thermophysical Property Measurement of High-temperature Oxide Melt by Aerodynamic Levitation," Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, vol. 56, s. 58-66, 2022.
[57]
X. Li et al., "Two-phase flow patterns identification in porous media using feature extraction and SVM," International Journal of Multiphase Flow, vol. 156, 2022.
[58]
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.
[59]
Y. Xiang et al., "A scoping study on debris bed formation from metallic melt coolant interactions," Nuclear Engineering and Design, vol. 385, 2021.
[60]
J. Lu et al., "An improved sectional model to simulate multi-component aerosol dynamics in a containment of pressurized water reactor," Journal of Aerosol Science, vol. 157, 2021.
[61]
S. Wei et al., "Development and validation of transient thermal-hydraulic evaluation code for a lead-based fast reactor," International Journal of Energy Research, vol. 45, no. 8, s. 12215-12233, 2021.
[62]
P. Yu och W. Ma, "Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs," Progress in nuclear energy (New series), vol. 139, 2021.
[63]
J. Liu et al., "Linear stability of a fluid mud–water interface under surface linear long travelling wave based on the Floquet theory," European journal of mechanics. B, Fluids, vol. 86, s. 37-48, 2021.
[64]
J. Xing et al., "Scaling analysis and evaluation for the design of integral test facility of HPR1000 containment (PANGU)," Nuclear Engineering and Design, vol. 373, 2021.
[65]
P. Yu och W. Ma, "A modified theta projection model for creep behavior of RPV steel 16MND5," Journal of Materials Science & Technology, vol. 47, s. 231-242, 2020.
[66]
P. Yu och W. Ma, "Comparative analysis of reactor pressure vessel failure using two thermo-fluid-structure coupling approaches," Nuclear Engineering and Design, vol. 368, 2020.
[67]
Y. Chen och W. Ma, "Development and application of a surrogate model for quick estimation of ex-vessel debris bed coolability," Nuclear Engineering and Design, vol. 370, 2020.
[68]
Y. -. Zhu et al., "Experimental Study of Critical Heat Flux on a Graphite Film," Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics, vol. 41, no. 3, s. 643-647, 2020.
[69]
J. Liu et al., "Influence of an External Perpendicular Oscillation on Stability of a Vertical Falling Liquid Film," Microgravity, science and technology, vol. 32, no. 5, s. 787-805, 2020.
[70]
S. Gong et al., "Orientation effect on heat transfer coefficient of a downward surface for flow boiling in a rectangular channel under low flow rate," International Journal of Heat and Mass Transfer, vol. 153, 2020.
[71]
Y. Chen och W. Ma, "Uncertainty quantification for TRACE simulation of FIX-II No. 5052 test," Annals of Nuclear Energy, vol. 143, 2020.
[72]
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.
[73]
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.
[74]
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.
[75]
Z. Huang och W. Ma, "On the quench of a debris bed in the lower head of a Nordic BWR by coolant injection through control rod guide tubes," Nuclear Engineering and Design, vol. 351, s. 189-202, 2019.
[76]
L. Manickam et al., "Oxidation of molten zirconium droplets in water," Nuclear Engineering and Design, vol. 354, 2019.
[77]
Z. Huang och W. Ma, "Performance of a passive cooling system for spent fuel pool using two-phase thermosiphon evaluated by RELAP5/MELCOR coupling analysis," Annals of Nuclear Energy, vol. 128, s. 330-340, 2019.
[78]
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.
[79]
Y. Mei et al., "A study on steam-water two phase flow distribution in a rectangular channel with different channel orientations," Experimental Thermal and Fluid Science, vol. 99, s. 219-232, 2018.
[80]
Z. Huang och W. Ma, "Numerical investigation on quench of an ex-vessel debris bed at prototypical scale," Annals of Nuclear Energy, vol. 122, s. 47-61, 2018.
[81]
K. Wang et al., "On the Relation between Nucleation Site Density and Critical Heat Flux of Pool Boiling," Heat Transfer Engineering, vol. 39, no. 17-18, s. 1498-1506, 2018.
[82]
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.
[83]
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.
[84]
Z. Huang och W. Ma, "Validation and application of the MEWA code to analysis of debris bed coolability," Nuclear Engineering and Design, vol. 327, s. 22-37, 2018.
[85]
K. Wang et al., "Experimental Study on the Dynamics of a Thin Liquid Film under Shearing Force," Jixie Gongcheng Xuebao/Journal of Mechanical Engineering, vol. 53, no. 24, s. 70-76, 2017.
[86]
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.
[87]
H. Gu et al., "Investigation on contact angle measurement methods and wettability transition of porous surfaces," Surface & Coatings Technology, vol. 292, s. 72-77, 2016.
[88]
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.
[89]
Z. Huang och W. Ma, "Performance evaluation of passive containment cooling system of an advanced PWR using coupled RELAP5/GOTHIC simulation," NUCLEAR ENGINEERING AND DESIGN, vol. 310, s. 83-92, 2016.
[90]
S. Thakre och W. Ma, "3D simulations of the hydrodynamic deformation of melt droplets in a water pool," Annals of Nuclear Energy, vol. 75, s. 123-131, 2015.
[91]
S. Thakre, L. Manickam och W. Ma, "A numerical simulation of jet breakup in melt coolant interactions," Annals of Nuclear Energy, vol. 80, s. 467-475, 2015.
[92]
S. Gong et al., "An investigation on dynamic thickness of a boiling liquid film," International Journal of Heat and Mass Transfer, vol. 90, s. 636-644, 2015.
[93]
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.
[94]
X. Cheng et al., "European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems," Nuclear Engineering and Design, vol. 290, s. 2-12, 2015.
[95]
S. Gong, W. Ma och H. Gu, "An experimental investigation on bubble dynamics and boiling crisis in liquid films," International Journal of Heat and Mass Transfer, vol. 79, s. 694-703, 2014.
[96]
S. Thakre, L. Li och W. Ma, "An experimental study on coolability of a particulate bed with radial stratification or triangular shape," Nuclear Engineering and Design, vol. 276, s. 54-63, 2014.
[97]
K. Wang, B. Bai och W. Ma, "An improved liquid film model to predict the CHF based on the influence of churn flow," Applied Thermal Engineering, vol. 64, no. 1-2, s. 422-429, 2014.
[98]
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.
[99]
T. Kozlowski et al., "Analysis of the OECD/NRC Oskarshamn-2 BWR stability benchmark," Annals of Nuclear Energy, vol. 67, s. 4-12, 2014.
[100]
J. Peltonen, W. Ma och T. Kozlowski, "Effective spatial mapping for coupled code analysis of thermal-hydraulics/neutron-kinetics of boiling water reactors," Annals of Nuclear Energy, vol. 63, s. 461-485, 2014.
[101]
N. Chikhi et al., "Evaluation of an effective diameter to study quenching and dry-out of complex debris bed," Annals of Nuclear Energy, vol. 74, s. 24-41, 2014.
[102]
I. Gajev, W. Ma och T. Kozlowski, "Sensitivity analysis of input uncertain parameters on BWR stability using TRACE/PARCS," Annals of Nuclear Energy, vol. 67, s. 49-58, 2014.
[103]
R. Meignen et al., "Status of steam explosion understanding and modelling," Annals of Nuclear Energy, vol. 74, s. 125-133, 2014.
[104]
K. Wang, B. Bai och W. Ma, "A model for droplet entrainment in churn flow," Chemical Engineering Science, vol. 104, s. 1045-1055, 2013.
[105]
S. Thakre, W. Ma och L. Li, "A numerical analysis on hydrodynamic deformation of molten droplets in a water pool," Annals of Nuclear Energy, vol. 53, s. 228-237, 2013.
[106]
S. Gong, W. Ma och L. Li, "An experimental study on the effect of liquid film thickness on bubble dynamics," Applied Thermal Engineering, vol. 51, no. 1-2, s. 459-467, 2013.
[107]
K. Wang, B. Bai och W. Ma, "Huge wave and drop entrainment mechanism in gas-liquid churn flow," Chemical Engineering Science, vol. 104, s. 638-646, 2013.
[108]
I. Gajev, W. Ma och T. Kozlowski, "Space–time convergence analysis on BWR stability using TRACE/PARCS," Annals of Nuclear Energy, vol. 51, s. 295-306, 2013.
[109]
K. Wang et al., "A physical model for huge wave movement in gas-liquid churn flow," Chemical Engineering Science, vol. 79, s. 19-28, 2012.
[110]
L. Li, W. Ma och S. Thakre, "An experimental study on pressure drop and dryout heat flux of two-phase flow in packed beds of multi-sized and irregular particles," Nuclear Engineering and Design, vol. 242, s. 369-378, 2012.
[111]
L. Li, S. Gong och W. Ma, "Experimental Study of Two-Phase Flow Regime and Pressure Drop in a Particulate Bed Packed with Multidiameter Particles," Nuclear Technology, vol. 177, no. 1, s. 107-118, 2012.
[112]
S. Gong, W. Ma och T.-N. Dinh, "Simulation and validation of the dynamics of liquid films evaporating on horizontal heater surfaces," Applied Thermal Engineering, vol. 48, s. 486-494, 2012.
[113]
S. Gong, W. Ma och T.-N. Dinh, "An experimental study of rupture dynamics of evaporating liquid films on different heater surfaces," International Journal of Heat and Mass Transfer, vol. 54, no. 7-8, s. 1538-1547, 2011.
[114]
L. Li och W. Ma, "Experimental Study on the Effective Particle Diameter of a Packed Bed with Non-Spherical Particles," Transport in Porous Media, vol. 89, no. 1, s. 35-48, 2011.
[115]
W. Ma et al., "Experimental and numerical study on lead-bismuth heat transfer in a fuel rod simulator," Journal of Nuclear Materials, vol. 415, no. 3, s. 415-424, 2011.
[116]
L. Li och W. Ma, "Experimental characterization of the effective particle diameter of a particulate bed packed with multi-diameter spheres," Nuclear Engineering and Design, vol. 241, no. 5, s. 1736-1745, 2011.
[117]
M. Buerger et al., "Coolability of particulate beds in severe accidents : Status and remaining uncertainties," Progress in nuclear energy (New series), vol. 52, no. 1, s. 61-75, 2010.
[118]
S. Gong, W. Ma och T.-N. Dinh, "Diagnostic techniques for the dynamics of a thin liquid film under forced flow and evaporating conditions," MICROFLUID NANOFLUID, vol. 9, no. 6, s. 1077-1089, 2010.
[119]
L. Li et al., "Dynamic characteristics of molten droplets and hot particles falling in liquid pool," Frontiers of Energy and Power Engineering in China, vol. 4, no. 2, s. 246-251, 2010.
[120]
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.
[121]
M. Buck et al., "The LIVE program : Results of test L1 and joint analyses on transient molten pool thermal hydraulics," Progress in nuclear energy (New series), vol. 52, no. 1, s. 46-60, 2010.
[122]
W. Ma och T.-N. Dinh, "The effects of debris bed's prototypical characteristics on corium coolability in a LWR severe accident," Nuclear Engineering and Design, vol. 240, no. 3, s. 598-608, 2010.
[123]
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.
[124]
W. Ma et al., "Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers," Nuclear Engineering and Design, vol. 239, no. 7, s. 1323-1330, 2009.
[125]
Z. L. Yang och W. Ma, "Direct numerical simulation of dynamic three-fluid flow," Progress in Computational Fluid Dynamics, An International Journal, vol. 7, no. 2-4, s. 176-182, 2007.
[126]
W. Ma, A. Karbojian och B. R. Sehgal, "Experimental study on natural circulation and its stability in a heavy liquid metal loop," Nuclear Engineering and Design, vol. 237, no. 15-17, s. 1838-1847, 2007.
[127]
W. Ma et al., "Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis," Nuclear Engineering and Design, vol. 236, no. 13, s. 1422-1444, 2006.
Konferensbidrag
[128]
L. Chen et al., "A Numerical Study of Melt Penetration into a Particulate Bed," i Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, 2023, s. 660-669.
[129]
Y. Gong et al., "Surface Tension Measurement of Molten Zirconia with Aerodynamic Levitation and Laser Heating," i Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, 2023.
[130]
Z. Liu et al., "Transient Cooling Investigation of A Conceptual Core Catcher Design with Embedded Cooling Tubes Using A GOTHIC 3D Model," i Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023, 2023, s. 3917-3930.
[131]
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.
[132]
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.
[133]
Q. Guo et al., "A design study on an aerodynamic levitation system for droplet preparation in steam explosion experiment," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[134]
Y. Zhang et al., "A feasibility study on application of redundancy sensors estimation technique to nuclear power plants," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[135]
K. Wang och W. Ma, "An experimental study on the dynamics of a liquid film under shearing force and thermal influence," i Proceedings of the Thermal and Fluids Engineering Summer Conference, 2019, s. 1093-1101.
[136]
Z. Qi et al., "Application of nonlinear principal component analysis technique to nuclear power plants," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[137]
Y. Chen och W. Ma, "Development of surrogate model for debris bed coolability analysis," i 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, s. 6770-6779.
[138]
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.
[139]
W. Li et al., "On improvement of a conditional mornitoring technique for condition-based maintenance," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[140]
Z. Qi et al., "Sensor fault detection in nuclear power plant using auto-associative neural network," i International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[141]
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.
[142]
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.
[143]
Y. Chen och W. Ma, "Sensitivity and uncertainty analysis of trace simulation against FIx-II experiments," i 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.
[144]
K. Wang, Y. Zhang och W. Ma, "An experimental study on the dynamics of a liquid film under shearing force and thermal influence," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, 2015, s. 3668-3677.
[145]
L. Manickam, S. Thakre och W. Ma, "An experimental study on void generation around hot metal partcle quenched into water pool," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, 2015, s. 6569-6578.
[146]
H. Zhang, Z. Huang och W. Ma, "MELCOR analysis of early containment venting risk in a severe accident scenario of boiling water reactor," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, s. 446-457.
[147]
Z. Huang, W. Ma och S. Thakre, "Validation of the MEWA code agsinst POMECO-HT experiments and cool ability analysis of stratified debris BEDS," i International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, 2015, s. 3279-3291.
[148]
S. Thakre och W. Ma, "An experimental study on the coolability of stratified debris beds," i International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 2014, s. 1107-1112.
[149]
Y. Chen, M. Weimin och L. Cui, "Numerical investigation of Fukushima Daiichi-2 SBO scenario," i International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 2014, s. 995-1003.
[150]
L. Manickam, S. Thakre och W. Ma, "Simultaneous Visual Acquisition of Melt Jet Breakup in Water by High Speed Videography and Radiography," i The 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10); Okinawa, Japan, Dec. 14-18, 2014, 2014.
[151]
I. Gajev, W. Ma och T. Kozlowski, "Uncertainty analysis of the OECD/NRC Oskarshamn-2 BWR stability Benchmark," i Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014, 2014.
[152]
M. Xing et al., "Validation of trace code against ROSA/LSTF test for SBLOCA of pressure vessel upper-head small break," i 2013 21st International Conference on Nuclear Engineering, ICONE 2013 : Volume 4: Thermal Hydraulics, 2014.
[153]
Y. Zhang, W. Ma och S. Gong, "An experimental study on liquid film dynamics and interfacial wave of air-water two-phase flow in a horizontal channel," i 2013 21st International Conference on Nuclear Engineering, ICONE 2013 : Volume 4: Thermal Hydraulics, 2013.
[154]
S. Thakre och W. Ma, "Numerical Analysis of Reactor Scale Ex-vessel Fuel Coolant Interactions Phenomena Using MC3D Code," i The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 Pisa, Italy, May 12-17, 2013, 2013, s. 446.
[155]
X. Hu, M. Xing och W. Ma, "Trace validation against loca transients performed on fix-II facility," i 2013 21st International Conference on Nuclear Engineering : Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled CodesChengdu, China, July 29–August 2, 2013, 2013.
[156]
A. Miassoedov et al., "Corium and debris coolability studies performed in the severe accident research network of excellence (SARNET2)," i Proceedings Of The 20th International Conference On Nuclear Engineering And The ASME 2012 Power Conference - 2012, Vol 2, 2012, s. 383-392.
[157]
W. Ma et al., "Progress in melt pool behavior and coolability in the lower head of a light water reactor," i ERMSAR-2012, 2012.
[158]
I. Gajev, T. Kozlowski och W. Ma, "Space-time convergence study based on OECD Ringhals-1 Stability Benchmark," i Transactions of the American Nuclear Society : Volume 106, 2012, 2012, s. 984-987.
[159]
S. Thakre, L. Li och W. Ma, "A Numerical Analysis on the Hydrodynamics of a Single Droplet in a Water Pool," i Proceedings of the international congress on advances in nuclear power plants : ICAPP2011, 2011.
[160]
S. Gong, L. Li och W. Ma, "An Experimental Study on Bubble Dynamics of High-Heat-Flux Boiling in a Horizontal Liquid Layer," i Proceedings of the 2011 international congress on advances in nuclear power plants : ICAPP2011, 2011.
[161]
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.
[162]
L. Li, S. Thakre och W. Ma, "An Experimental Study on Two-Phase Flow and Coolability of Particulate Beds Packed with Multi-Size Particles," i Proceedings of NURETH-14 The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 2011.
[163]
L. Li och W. Ma, "Experimental Investigations on Friction Laws and Dryout Heat Flux of Particulate Bed Packed with Multi-Size Spheres or Irregular Particles," i Proceedings of 19th International Conference on Nuclear Engineering (ICONE19), 2011.
[164]
L. Li och W. Ma, "Experimental Study on the Effective Particle Diameter of a Packed Bed with Non-Spherical Particles," i Topical Meeting of SARNET2 WP5-COOL, June 29- July 1, Stockholm, Sweden, 2011, 2011.
[165]
R. Thiele, H. Anglart och W. Ma, "Investigation of the Influence of Turbulence Models on the Prediction of Heat Transfer to Low Prandtl Number Fluids," i The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, 2011.
[166]
S. Gong, W. Ma och T.-N. Dinh, "Measurement of Film Dynamics in a Boiling Liquid Film," i Proceedings of NURETH-14 The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 2011.
[167]
W. Ma, "Prediction of dryout heat flux of volumetrically heated particulate beds packed with multi-size particles," i Proceedings of NURETH-14 The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 2011.
[168]
L. Li och W. Ma, "Toward Quantification of Debris Bed Coolability in Corium Risk Assessment," i 2011 ANS Winter Meeting and Nuclear Technology Expo, 2011, s. 1060-1061.
[169]
S. Gong och W. Ma, "An Experimental Study on Boiling Phenomenon in a Liquid Layer," i 7th International Conference on Multiphase Flow - ICMF 2010 Proceedings, 2010.
[170]
W. Ma, L. Li och A. Karbojian, "An experimental study on coolability of volumetrically heated particulate beds of prototypical characteristics," i Proceeding of the 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010.
[171]
L. Li och W. Ma, "An experimental study on two-phase flow regimes and frictional pressure drop in porous media packed with multidiameter spheres," i Proceedings of 7th international conference on multiphase flow (ICMF2010), 2010.
[172]
W. Ma och A. Karbojian, "Characteristics of frictional pressure drop of heavy liquid metal flow in a single fuel rod simulator," i Proceeding of the 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010.
[173]
L. X. Li et al., "Experimental investigation on the dynamic characteristics of molten droplets and high-temperature particles falling in coolant," i 6TH INTERNATIONAL SYMPOSIUM ON MULTIPHASE FLOW, HEAT MASS TRANSFER AND ENERGY CONVERSION, 2010, s. 292-299.
[174]
C. Journeau et al., "A European joint work plan on molten core concrete interaction," i International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009, 2009, s. 1058-1065.
[175]
W. Ma, A. Karbojian och T.-N. Dinh, "An experimental study of transient thermal-hydraulics in LBE-cooled system using a single rod simulator," i Proceeding of the 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2009.
[176]
S. Gong, W. Ma och T.-N. Dinh, "Measurement of thin liquid film dynamics under forced flow and evaporating condition," i Proceeding of ECI International Conference on Boiling Heat Transfer, 2009.
[177]
W. Ma och C.-T. Tran, "On the Effectiveness of CRGT Cooling as a Severe Accident Management Measure for BWRs," i Proceedings of OECD/NEA Workshop on Implementation of Severe Accident Management Measures, 2009.
[178]
S. Roshan Ghias et al., "A study of reactor systems during a loss of offsite electric power in Forsmark-1 Plant," i Proceedings of 2007 International congress on advances in nuclear power plants (ICAPP 2007) : Volume 4, 2008, s. 2642-2651.
[179]
J. Van Dorsselaere et al., "ASTEC extension to other reactor types than Generation II PWR," i Proc. of ERMSAR 2008, 2008.
[180]
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.
[181]
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.
[182]
C. Journeau et al., "European Research on the Corium issues within the SARNET network of excellence," i International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2008, s. 1172-1181.
[183]
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.
[184]
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.
[185]
W. Ma och T.-N. Dinh, "A study on effects of debris bed prototypicality on coolability," i Proceedings of the 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH12), 2007.
[186]
W. Ma et al., "Analysis of the effect of bed inhomogeneity on debris coolability," i Proceedings of the 15th International Conference on Nuclear Engineering (ICONE15), 2007.
[187]
W. Ma och T.-N. Dinh, "Coolability analysis of bottom-fed debris bed in a LWR severe accident," i Proceedings of the 15th International Conference on Nuclear Engineering (ICONE15), 2007.
[188]
W. Ma et al., "Thermal-hydraulic performance of lead-bismuth eutectic in a straight-tube and a u-tube heat exchangers," i Proceedings of the 12th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), 2007.
[189]
W. Ma, A. Karbojian och B. Sehgal, "Experiments on Natural circulation of lead-bismuth in the TALL test facility," i Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), 2005.
[190]
B. Sehgal, W. Ma och A. Karbojian, "Thermal-Hydraulic Experiments on the Tall LBE Test Facility," i Utilisation and Reliability of High Power Proton Accelerators Workshop Proceedings, Daejeon, Republic of Korea, 16-19 May 2004, 2004, s. 465-476.
Icke refereegranskade
Kapitel i böcker
[191]
W. Ma, "Chapter 2.6 of the book "Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology"," i Nuclear Safety in Light Water Reactors : Severe Accident Phenomenology, Bal Raj Sehgal red., 1. uppl. : Academic Press, 2012.
Rapporter
[192]
T. Kozlowski et al., "Deterministic Safety Analysis Group. Review for the period of 2008 – 2010," Stockholm, 2010.
Övriga
[193]
P. Yu och W. Ma, "Comparative Analysis of Reactor Pressure Vessel Failure using Two Thermo-Fluid-Structure Coupling Approaches," (Manuskript).
[194]
P. Yu och W. Ma, "Development of a Lumped-Parameter Code for Efficient Assessment of In-Vessel Melt Retention Strategy of LWRs," (Manuskript).
[195]
Z. Huang och W. Ma, "On the quench of a debris bed in the lower head of a Nordic BWR by coolant injection through control rod guide tubes," (Manuskript).
[196]
S. Thakre, W. Ma och R. Meignen, "Uncertainty analysis in quantification of steam explosion energetics in a reference Nordic BWR," (Manuskript).
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2024-11-20 01:11:39