Publications

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

Nuclear Power Safety

[1]
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.
[2]
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.
[3]
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.
[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]
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.
[7]
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.
[8]
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.
[9]
H. Y. Kim et al., "In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor," Science and Technology of Nuclear Installations, 2018.
[10]
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.
[11]
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.
[12]
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.
[13]
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.
[14]
[15]
J. Wallenius, "Maximum efficiency nuclear waste transmutation," Annals of Nuclear Energy, vol. 125, pp. 74-79, 2019.
[17]
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.
[18]
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.
[19]
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.
[20]
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.
[22]
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.
[23]
[24]
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.
[25]
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.
[26]
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.
[28]
L. Manickam et al., "Oxidation of molten zirconium droplets in water," Nuclear Engineering and Design, vol. 354, 2019.
[29]
B. R. Sehgal, "Perspectives on LWR severe accidents and public risks Preface," Nuclear Engineering and Design, vol. 354, 2019.
[30]
Z. Qi et al., "Application of nonlinear principal component analysis technique to nuclear power plants," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[31]
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.
[32]
W. Li et al., "On improvement of a conditional mornitoring technique for condition-based maintenance," in International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.
[34]
V. Moreau et al., "Pool CFD modelling : lessons from the SESAME project," Nuclear Engineering and Design, vol. 355, 2019.
[35]
S. Estévez-Albuja et al., "Modelling of a Nordic BWR containment and suppression pool behavior during a LOCA with GOTHIC 8.1," Annals of Nuclear Energy, vol. 136, 2020.
[36]
S. Galushin and P. Kudinov, "The effect of severe accident scenarios on in-vessel debris relocation in Nordic BWRs," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 1957-1970.
[37]
D. Grishchenko et al., "TALL-3D open and blind benchmark on natural circulation instability," Nuclear Engineering and Design, vol. 358, 2020.
[38]
X. Wang et al., "Pre-test analysis for HYMERES-2 PANDA tests series for steam injection into pool through spargers," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 6190-6203.
[39]
X. Wang et al., "Post-test calibration of the Effective Momentum Source (EMS) model for steam injection through multi-hole spargers.," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 6176-6189.
[41]
P. Kudinov et al., "Development of risk oriented accident analysis methodology (ROAAM+) for assessment of ex-vessel severe accident management effectiveness," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 2519-2535.
[42]
Q. Guo et al., "Effects of salinity in coolant on steam explosion," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 4556-4567.
[43]
A. Papukchiev et al., "Validation of the system thermal-hydraulics code ATHlet for the simulation of transient lead-bismuth eutectic flows," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 810-822.
[44]
D. Grishchenko and P. Kudinov, "Validation of a full model for the analysis of ex-vessel steam explosion in LWRs," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 4568-4574.
[45]
D. Grishchenko, S. Galushin and P. Kudinov, "Risk of containment failure due to ex-vessel steam explosion for Nordic BWRs," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 4032-4038.
[46]
P. Yu and W. Ma, "A modified theta projection model for creep behavior of RPV steel 16MND5," Journal of Materials Science & Technology, vol. 47, pp. 231-242, 2020.
[47]
Y. Chen and W. Ma, "Development of surrogate model for debris bed coolability analysis," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 6770-6779.
[48]
A. Papukchiev, D. Grishchenko and P. Kudinov, "Importance of conjugate heat transfer modeling in transient CFD simulations," in 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2019, pp. 615-626.
[49]
P. Yu, "Modelling and Simulation of Reactor Pressure Vessel Failure during Severe Accidents," Doctoral thesis Sweden : KTH Royal Institute of Technology, TRITA-SCI-FOU, 2020:13, 2020.
[50]
C. Ekberg et al., "Fuel fabrication and reprocessing issues : the ASGARD project," EPJ Nuclear Sciences & Technologies., vol. 6, 2020.
Page responsible:Walter Villanueva
Belongs to: Nuclear power safety
Last changed: Aug 24, 2018