Publications

The list below contains the last 50 of Nuclear Power Safetys publications.

Nuclear Power Safety

[1]
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.
[2]
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.
[3]
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.
[5]
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.
[6]
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.
[7]
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.
[9]
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.
[11]
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.
[12]
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.
[13]
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.
[14]
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.
[15]
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.
[16]
[17]
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.
[18]
H. Y. Kim et al., "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor," Science and Technology of Nuclear Installations, 2018.
[19]
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.
[20]
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.
[21]
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.
[22]
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.
[23]
[24]
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.
[25]
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.
[26]
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.
[28]
[29]
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.
[30]
S. Basso, "Particulate Debris Spreading and Coolability," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2017:15, 2017.
[31]
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.
[32]
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.
[33]
J. Wallenius, "Maximum efficiency nuclear waste transmutation," Annals of Nuclear Energy, vol. 125, pp. 74-79, 2019.
[35]
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.
[36]
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.
[37]
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.
[38]
[40]
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.
[41]
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.
[42]
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.
[43]
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.
[45]
B. R. Sehgal, "Perspectives on LWR severe accidents and public risks Preface," Nuclear Engineering and Design, vol. 354, 2019.
[46]
L. Manickam et al., "Oxidation of molten zirconium droplets in water," Nuclear Engineering and Design, vol. 354, 2019.
[47]
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.
[48]
Z. Qi et al., "Application of nonlinear principal component analysis technique to nuclear power plants," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[49]
W. Li et al., "On improvement of a conditional mornitoring technique for condition-based maintenance," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
Page responsible:Walter Villanueva
Belongs to: Nuclear power safety
Last changed: Aug 24, 2018