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Engineering Sciences and Information Technology
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Journal Articles
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Science and Technology of Nuclear Installations
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Hindawi Publishing Corporation Cairo, Egypt :
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Journal Articles
Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
By: Yousif, Eltayeb; Zhang, Zhijian; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2017 (2017), pp.1-13, 13 p.
Journal Articles
The Sliding and Overturning Analysis of Spent Fuel Storage Rack Based on Dynamic Analysis Model
By: Liu, Yu; Lu, Dao-gang; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2016 (2016), pp.1-11, 11 p.
Journal Articles
A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit
By: Mandelli, Diego; Prescott, Steven; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2015 (2015), pp.1-14, 14 p.
Journal Articles
HTR-Based Power Plants’ Performance Analysis Applied on Conventional Combined Cycles
By: Carril, José Carbia; Insua, Álvaro Baaliña; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2015 (2015), pp.1-11, 11 p.
Journal Articles
SIMMER-III Analyses of Local Fuel-Coolant Interactions in a Simulated Molten Fuel Pool: Effect of Coolant Quantity
By: Cheng, Songbai; Suzuki, T.; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2015 (2015), pp.1-14, 14 p.
Journal Articles
Heat Transfer Analysis of Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition in Tank
By: Men, Qiming; Wang, Xuesheng; Mavko, Borut…[et al.]. Science and Technology of Nuclear Installations. No. 2014 (2014), pp.1-8, 8 p.
Journal Articles
Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor
By: Zhang, Fan; Mavko, Borut; Yuan, Bo…[et al.]. Science and Technology of Nuclear Installations. No. 2014 (2014), pp.1-7, 7 p.
Journal Articles
Simplification of State Transition Diagrams in Average Unavailability Analysis by Using Generalized Perturbation Theory
By: Frutuoso e Melo, Paulo Fernando F.; Mavko, Borut; Alvim, Antonio Carlos Marques…[et al.]. Science and Technology of Nuclear Installations. No. 2014 (2014), pp.1-8, 8 p.
Journal Articles
Effective Atomic Number Determination of Rare Earth Oxides with Scattering Intensity Ratio
By: Turşucu, A.; Demir, Demet; Onder, Pinar…[et al.]. Science and Technology of Nuclear Installations. No. 2013 (2013), pp.1-6, 6 p.
Journal Articles
Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Steady State BFBT Data
By: Jaeger, Wadim; Montero Mayorga, Francisco Javier; Queral, Cesar…[et al.]. Science and Technology of Nuclear Installations. No. 2013 (2013), pp.1-11, 11 p.
Journal Articles
Uncertainty and Sensitivity Studies with TRACE-SUSA and TRACE-DAKOTA by Means of Transient BFBT Data
By: Jaeger, Wadim; Montero Mayorga, Francisco Javier; Queral, Cesar…[et al.]. Science and Technology of Nuclear Installations. No. 2013 (2013), pp.1-9, 9 p.
Journal Articles
RELAP5MOD3.3 Best Estimate Analyses for Human Reliability Analysis
By: Prošek, Andrej; Mavko, Borut; Cavlina, Nikola. Science and Technology of Nuclear Installations. No. 2010 (2010), pp.1-12, 12 p.
Journal Articles
Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code
By: Končar, Boštjan; Mavko, Borut; Kljenak, Ivo. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-8, 8 p.
Journal Articles
RELAP5MOD3.3 Code Validation with Plant Abnormal Event
By: Prošek, Andrej; Mavko, Borut; Adorni, Martina. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-10, 10 p.
Journal Articles
Dynamics of Fluid Fuel Reactors in the Presence of Periodic Perturbations
By: Dulla, S.; Nicolino, C.; Mavko, Borut. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-11, 11 p.