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تقييد النتائج
التخصصات الرئيسية
العلوم الهندسية و تكنولوجيا المعلومات
(321)
نوع البيانات
مقالات
(733)
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الإنجليزية
(733)
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(733)
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مشتوا، نعمان
(3)
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Science and Technology of Nuclear Installations
(733)
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مقالات
The Use of Th in HTR : State of the Art and Implementation in ThPu Fuel Cycles
By: Lomonaco, Guglielmo; Shwageraus, Eugene; Kuijper, Jim…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-13, 13 p.
مقالات
Influence of Modelling Options in RELAP5SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity
By: Šadek, Siniša; Špalj, Srđan; Glaser, Bruno…[et al.]. Science and Technology of Nuclear Installations. No. 2010 (2010), pp.1-11, 11 p.
مقالات
An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project
By: Tiselj, Iztok; Martin, A.; Kyrki-Rajamäki, R.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-13, 13 p.
مقالات
New Methods for Evaluation of Spent Fuel Condition during Long-Term Storage in Slovakia
By: Mikloš, M.; Kršjak, V.; Iyer, Kannan. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-5, 5 p.
مقالات
Assessment of LWR-HTR-GCFR Integrated Cycle
By: Bomboni, Eleonora; Lomonaco, Guglielmo; Kuijper, Jim…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-14, 14 p.
مقالات
Application of CFD Codes in Nuclear Reactor Safety Analysis
By: Hoehne, Thomas; Rohde, U.; Giot, Michel…[et al.]. Science and Technology of Nuclear Installations. No. 2010 (2010), pp.1-8, 8 p.
مقالات
Computational Methods for Multidimensional Neutron Diffusion Problems
Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-11, 11 p.
مقالات
The SPES3 Experimental Facility Design for the IRIS Reactor Simulation
By: Storrick, Gary; Meloni, Paride; Monti, Stefano…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
Modelling of HTR Confinement Behaviour during Accidents Involving Breach of the Helium Pressure Boundary
By: Herranz, Luis E.; Ramlakan, Alastair; Kuijper, Jim…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-11, 11 p.
مقالات
Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors
By: Cheng, Lap-Yan; Wei, Thomas Y. C.; Mitchell, Colin. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-13, 13 p.
مقالات
Non-Boussinesq Integral Model for Horizontal Turbulent Buoyant Round Jets
By: Xiao, J.; Breitung, W.; Cheng, X.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-7, 7 p.
مقالات
Gas-Cooled Fast Reactor : A Historical Overview and Future Outlook
By: van Rooijen, W. F. G.; Lomonaco, Guglielmo. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-11, 11 p.
مقالات
GASFLOW Validation with Panda Tests from the OECD SETH Benchmark Covering SteamAir and SteamHeliumAir Mixtures
By: Royl, Peter; Travis, John R.; Kim, Sang-Baik…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-13, 13 p.
مقالات
Role of Passive Safety Systems in Chinese Nuclear Power Development
By: Yang, Yanhua; Ouyang, Y.; Araneo, Dino A.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-7, 7 p.
مقالات
Physics Features of TRU-Fueled VHTRs
By: Lewis, Tom G.; Tsvetkov, Pavel V.; Kloosterman, Jan Leen. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-7, 7 p.
مقالات
Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor
By: van Rooijen, W. F. G.; Kloosterman, Jan Leen; Lomonaco, Guglielmo. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-9, 9 p.
مقالات
GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides
Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-8, 8 p.
مقالات
CFD Application to Hydrogen Risk Analysis and PAR Qualification
By: Xiong, Jinbiao; Yang, Yanhua; Cheng, X.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-10, 10 p.
مقالات
Selected Papers from the International Conference on Nuclear Energy for New Europe 2007
By: Jenčič, Igor; Kljenak, Ivo; Adorni, Martina. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-1, 1 p.
مقالات
CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX
By: Hoehne, Thomas; Anis, Bousbia Salah. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-7, 7 p.
مقالات
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor
By: Gou, Junli; Jia, Douna; Cheng, X.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
Experiments and Modelling Techniques for Heat and Mass Transfer in Light Water Reactors
By: Bucci, M.; Oriolo, F.; Cheng, X.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-11, 11 p.
مقالات
Computational Fluid Dynamics for Gas-Liquid Flows
By: Lucas, Dirk; Tiselj, Iztok; Moretti, Fabio…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-1, 1 p.
مقالات
Modelling of the Production of Source Neutrons from Low-Voltage Accelerated Deuterons on Titanium-Tritium Targets
By: Milocco, A.; Trkov, A.; Adorni, Martina. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Mechanistic Multidimensional Modeling of Forced Convection Boiling Heat Transfer
By: Podowski, Michael Z.; Podowski, Raf M.; Tiselj, Iztok. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-10, 10 p.
مقالات
CFD Analysis of a Slug Mixing Experiment Conducted on a VVER-1000 Model
By: Moretti, Fabio; Melideo, D.; Lisenkov, E.…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
CFD Code Validation against Stratified Air-Water Flow Experimental Data
By: Terzuoli, F.; Galassi, Maria Cristina; Kljenak, Ivo…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
By: Galassi, Maria Cristina; Morel, Christophe; Moretti, Fabio…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
Simulation of MASPn Experiments in MISTRA Test Facility with COCOSYS Code
By: Povilaitis, Mantas; Urbonavičius, Egidijus; Kljenak, Ivo. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design Preparation of the HCLL Breeder Blanket Mockup Experiment for ITER
By: Kodeli, I.; Jenčič, Igor. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
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.
مقالات
Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations
By: Péturaud, P.; Krepper, E.; Končar, Boštjan…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-14, 14 p.
مقالات
2
عدد الاستشهادات
في قاعدة ارسيف
CFD Simulation of Polydispersed Bubbly Two-Phase Flow around an Obstacle
By: Prasser, H.-M.; Seiler, N.; Tiselj, Iztok…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
Euler-Euler Large Eddy Simulation of a Square Cross-Sectional Bubble Column Using the Neptune_CFD Code
By: Boucker, M.; Smith, B. L.; Tiselj, Iztok…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-8, 8 p.
مقالات
A Second-Order Turbulence Model Based on a Reynolds Stress Approach for Two-Phase Flow—Part I : Adiabatic Cases
By: Mimouni, Stéphane; Morel, Christophe; Lucas, Dirk…[et al.]. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-14, 14 p.
مقالات
Power Distribution and Possible Influence on Fuel Failure in WWER-1000
By: Mikuš, Ján; Jenčič, Igor. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
Modeling of Multisize Bubbly Flow and Application to the Simulation of Boiling Flows with the Neptune_CFD Code
By: Morel, Christophe; Laviéville, Jérôme M.; Moretti, Fabio. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-8, 8 p.
مقالات
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
By: Meloni, Paride; Castiglia, Francesco; Kljenak, Ivo…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-8, 8 p.
مقالات
Theoretical and Numerical Study of Heat Transfer Deterioration in High Performance Light Water Reactor
By: Palko, David; Anglart, Henryk; Kljenak, Ivo. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
CFD Approaches for Modelling Bubble Entrainment by an Impinging Jet
By: Schmidtke, Martin; Lucas, Dirk; Moretti, Fabio. Science and Technology of Nuclear Installations. No. 2009 (2009), pp.1-12, 12 p.
مقالات
Machine Learning of the Reactor Core Loading Pattern Critical Parameters
By: Trontl, Krešimir; Pevec, Dubravko; Jenčič, Igor…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-6, 6 p.
مقالات
Analysis of TROI-13 Steam Explosion Experiment
By: Uršič, Mitja; Leskovar, Matjaž; Adorni, Martina. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-9, 9 p.
مقالات
Using Safety Margins for a German Seismic PRA
By: Obenland, Ralf; Bloem, Theodor; Adorni, Martina…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
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.
مقالات
Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor
By: Moormann, Rainer; Giot, Michel. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-14, 14 p.
مقالات
Comparison of Methods for Dependency Determination between Human Failure Events within Human Reliability Analysis
By: Čepin, Marko; Adorni, Martina. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Gamma Decay Heat Distribution in Core: A Known Issue Revisited
By: Petrangeli, Gianni; Sollima, Calogero; Glaeser, Horst. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
Coupling of Modular High-Temperature Gas-Cooled Reactor with Supercritical Rankine Cycle
By: Tang, Ying; Zhang, Zuoyi; Aksan, Nusret…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-9, 9 p.
مقالات
Deterministic Safety Technology for RBMK Reactors
By: Soloviev, S.; Sollima, Calogero; Uspuras, Eugenijus…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Flow Instabilities in Boiling Two-Phase Natural Circulation Systems : A Review
By: Nayak, A. K.; Vijayan, P. K.; Saha, Dilip. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-15, 15 p.
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