Publications

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

Nuclear Power Safety

[1]
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.
[2]
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.
[5]
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.
[6]
H. Y. Kim et al., "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor," Science and Technology of Nuclear Installations, 2018.
[7]
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.
[8]
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.
[9]
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.
[11]
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.
[12]
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.
[13]
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.
[14]
[15]
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.
[16]
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.
[17]
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.
[18]
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.
[20]
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.
[22]
[23]
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.
[24]
S. Basso, "Particulate Debris Spreading and Coolability," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2017:15, 2017.
[26]
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.
[27]
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.
[28]
S. Galusin et al., "An approach to joint application of integrated deterministic-probabilistic safety analysis and PSA Level 2 to severe accident issues in Nordic BWRs," in PSAM 2016 - 13th International Conference on Probabilistic Safety Assessment and Management2017, 2016.
[29]
S. Galushin and P. Kudinov, "Analysis of core degradation and relocation phenomena and scenarios in a Nordic-type BWR," NUCLEAR ENGINEERING AND DESIGN, vol. 310, pp. 125-141, 2016.
[30]
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.
[31]
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.
[32]
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.
[33]
S. Galushin and P. Kudinov, "Comparison of melcor code versions predictions of the properties of relocated debris in lower plenum of nordic BWR," in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.
[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, pp. 524-537, 2016.
[35]
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.
[36]
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.
[37]
I. Pazsit et al., "Developments in Core-Barrel Motion Monitoring and Applications to the Ringhals PWR Units," Nuclear science and engineering, vol. 182, no. 2, pp. 213-227, 2016.
[38]
S. Galushin and P. Kudinov, "Effect of severe accident scenario and modeling options in melcor on the properties of relocated debris in nordic BWR lower plenum," in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.
[40]
S. Basso, A. Konovalenko and P. Kudinov, "Effectiveness of the debris bed self-leveling under severe accident conditions," Annals of Nuclear Energy, vol. 95, pp. 75-85, 2016.
[41]
S. Basso, A. Konovalenko and P. Kudinov, "Empirical closures for particulate debris bed spreading induced by gas-liquid flow," Nuclear Engineering and Design, vol. 297, pp. 19-25, 2016.
[42]
A. Konovalenko et al., "Experimental investigation of particulate debris spreading in a pool," Nuclear Engineering and Design, vol. 297, pp. 208-219, 2016.
[43]
W. Ma, Y. Yuan and B. R. Sehgal, "In-Vessel Melt Retention of Pressurized Water Reactors : Historical Review and Future Research Needs," Engineering, vol. 2, no. 1, pp. 103-111, 2016.
[44]
H. Gu et al., "Investigation on contact angle measurement methods and wettability transition of porous surfaces," Surface & Coatings Technology, vol. 292, pp. 72-77, 2016.
[45]
S. E. Yakush and P. Kudinov, "Melt agglomeration influence on ex-vessel debris bed coolability," in 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2016.
[46]
I. Gallego-Marcos, W. Villanueva and P. Kudinov, "Modeling of Thermal Stratification and Mixing in a Pressure Suppression Pool Using GOTHIC," in NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, At Gyeongju, Korea, 2016.
[48]
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.
[49]
V. I. Almyashev et al., "Oxidation effects during corium melt in-vessel retention," Nuclear Engineering and Design, vol. 305, pp. 389-399, 2016.
[50]
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