The list below contains the last 50 of Nuclear Power Safetys publications.
Nuclear Power Safety
Z. Huang and W. Ma, "Validation and application of the MEWA code to analysis of debris bed coolability," Nuclear Engineering and Design, vol. 327, pp. 22-37, 2018.
Z. Huang and W. Ma, "Numerical investigation on quench of an ex-vessel debris bed at prototypical scale," Annals of Nuclear Energy, vol. 122, pp. 47-61, 2018.
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.
S. Sawalha et al., "Field measurements of supermarket refrigeration systems. Part II: Analysis of HFC refrigeration systems and comparison to CO2 trans-critical," Applied Thermal Engineering, vol. 111, no. 1, pp. 170-182, 2017.
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.
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.
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.
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.
J. Wallenius and S. Bortot, "A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics," Annals of Nuclear Energy, vol. 122, pp. 193-200, 2018.
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, pp. 22-37, 2019.
S. Bechta et al., "On the EU-Japan roadmap for experimental research on corium behavior," Annals of Nuclear Energy, vol. 124, pp. 541-547, 2019.
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, pp. 300-316, 2018.
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, pp. 219-232, 2018.
L. Manickam, "An Experimental Study on Melt Fragmentation, Oxidation and Steam Explosion during Fuel Coolant Interactions," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-SCI-FOU, 2018:54, 2018.
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, pp. 251-266, 2019.
M. Lou et al., "Design of the Online Gross gamma Monitoring Instrument at the Exit of the Helium Purification System in HTR-PM," Science and Technology of Nuclear Installations, 2018.
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, pp. 82-91, 2018.
H. Y. Kim et al., "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor," Science and Technology of Nuclear Installations, 2018.
I. Gallego Marcos, W. Villanueva and P. Kudinov, "Modelling of pool stratification and mixing induced by steam injectionthrough blowdown pipes," Annals of Nuclear Energy, vol. 112, pp. 624-639, 2018.
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, pp. 1498-1506, 2018.
C. Journeau et al., "Safest roadmap for corium experimental research in Europe," ASCE-ASME Journal of Risk and Uncertainty in Engineering Systems, Part B: Mechanical Engineering, vol. 4, no. 3, 2018.
S. Galushin and P. Kudinov, "Sensitivity analysis of debris properties in lower plenum of a Nordic BWR," Nuclear Engineering and Design, vol. 332, pp. 374-382, 2018.
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, pp. 36-45, 2018.
M. Jeltsov, W. Villanueva and P. Kudinov, "Steam generator leakage in lead cooled fast reactors : Modeling of void transport to the core," Nuclear Engineering and Design, vol. 328, pp. 255-265, 2018.
J. A. Zambaux et al., "Study on thermal fragmentation characteristics of a superheated alumina droplet," Annals of Nuclear Energy, vol. 119, pp. 352-361, 2018.
H. Li et al., "Thermal stratification and mixing in a suppression pool induced by direct steam injection," Annals of Nuclear Energy, vol. 111, pp. 487-498, 2018.
A. Dokhane et al., "Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone," Annals of Nuclear Energy, vol. 102, pp. 190-199, 2017.
V.-A. Phung, "Input Calibration, Code Validation and Surrogate Model Development for Analysis of Two-phase Circulation Instability and Core Relocation Phenomena," Doctoral thesis Stockholm : Kungliga Tekniska högskolan, TRITA-FYS, 2017:03, 2017.
L. Manickam, S. Bechta and W. Ma, "On the fragmentation characteristics of melt jets quenched in water," International Journal of Multiphase Flow, vol. 91, pp. 262-275, 2017.
S. Basso, "Particulate Debris Spreading and Coolability," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2017:15, 2017.
D. B. Lopukh et al., "Numerical Simulation of Induction Heating for Molten Pool heat Transfer Experiments in Slice Geometry," in 2018 INTERNATIONAL SCIENTIFIC MULTI-CONFERENCE ON INDUSTRIAL ENGINEERING AND MODERN TECHNOLOGIES (FAREASTCON), 2018.
S. E. Yakush and 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, pp. 895-905, 2019.
J. Wallenius, "Maximum efficiency nuclear waste transmutation," Annals of Nuclear Energy, vol. 125, pp. 74-79, 2019.
Z. Huang and 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, pp. 330-340, 2019.
F. Fichot et al., "A revised methodology to assess in-vessel retention strategy for high-power reactors," in PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 18, VOL 7, 2018.
M. Jolkkonen and Y. Mishchenko, "Manufacture and characterization of a UN-UO2 LWR composite fuel," in NURER 2018 - 6th International Conference on Nuclear and Renewable Energy Resources, Jeju, South Korea, 2018, 2018.
Z. Huang, "Numerical Investigations on Debris Bed Coolability and Mitigation Measures in Nordic Boiling Water Reactors," Doctoral thesis : KTH Royal Institute of Technology, TRITA-SCI-FOU, 2019:27, 2019.
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, pp. 67-85, 2019.
S. Galushin and 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.
M. R. Kaleibar et al., "Uncertainty quantification of Edwards high-pressure pipe behavior using complex system thermal-hydraulics codes," in ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), 2018.
S. Galushin and P. Kudinov, "Analysis of the effect of severe accident scenario on the vessel lower head failure in Nordic BWR using MELCOR code," in PSAM 2018 - Probabilistic Safety Assessment and Management, 2018.
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.
Z. Huang and 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, pp. 189-202, 2019.
M. Khan, N. Zhao and T. Xu, "Assessment of PECM as an efficient numerical analysis tool for investigating convective heat transfer phenomena during PCM melting," Journal of Energy Storage, vol. 24, 2019.
B. R. Sehgal, "Perspectives on LWR severe accidents and public risks Preface," Nuclear Engineering and Design, vol. 354, 2019.
L. Manickam et al., "Oxidation of molten zirconium droplets in water," Nuclear Engineering and Design, vol. 354, 2019.
P. Yu et al., "Coupled Thermo-Mechanical Creep Analysis For A Nordic BWR Lower Head Using Non-Homogeneous Debris Bed Configuration From MELCOR," in 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 2018.
Z. Qi et al., "Application of nonlinear principal component analysis technique to nuclear power plants," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
W. Li et al., "On improvement of a conditional mornitoring technique for condition-based maintenance," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
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, pp. 637-648, 2019.