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تقييد النتائج
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العلوم الهندسية و تكنولوجيا المعلومات
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Science and Technology of Nuclear Installations
(52)
الفترة:
نتائج البحث
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52
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الصلة
تاريخ النشر تصاعدي
تاريخ النشر تنازلي
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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
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
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
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
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
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
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.
مقالات
Scaling, Uncertainty, and 3D Coupled Code Calculations in Nuclear Technology
By: Frepoli, Cesare; Petruzzi, Alessandro. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-3, 3 p.
مقالات
Natural Circulation in Nuclear Reactor Systems
By: Saha, Dilip; Cleveland, John. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-1, 1 p.
مقالات
Accident Management in VVER-1000
By: D'Auria, Francesco; Muellner, N.; Cherubini, M.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
Evaluation of Heat Removal from RBMK-1500 Core Using Control Rods Cooling Circuit
By: Kaliatka, Algirdas; Uspuras, Eugenijus; Melikhov, Oleg I.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-8, 8 p.
مقالات
Effect of Loop Diameter on the Steady State and Stability Behaviour of Single-Phase and Two-Phase Natural Circulation Loops
By: Vijayan, P. K.; Saha, Dilip; Gartia, M. R.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-17, 17 p.
مقالات
Numerical Simulations and Design Optimization of the PHT Loop of Natural Circulation BWR
By: Durga Prasad, G. V.; Gopa Kishor, G.; Dixit, Uday S.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-12, 12 p.
مقالات
Wastes Management Through Transmutation in an ADS Reactor
By: Calgaro, Barbara; Forasassi, Giuseppe; Verboomen, Bernard…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-6, 6 p.
مقالات
SBWR Model for Steady-State and Transient Analysis
By: Espinosa-Paredes, Gilberto; Nuñez-Carrera, Alejandro; Saha, Dilip. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-18, 18 p.
مقالات
Natural Circulation Characteristics at Low-Pressure Conditions through PANDA Experiments and ATHLET Simulations
By: Paladino, Domenico; Paladino, Domenico; Schäfer, Frank…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-14, 14 p.
مقالات
Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout
By: Gaikwad, Avinash J.; Iyer, Kannan; Saha, Dilip…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-11, 11 p.
مقالات
Numerical Analysis of General Trends in Single-Phase Natural Circulation in a 2D-Annular Loop
By: Desrayaud, Gilles; Fichera, Alberto; Cleveland, John. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-10, 10 p.
مقالات
A Critical Review of the Recent Improvements in Minimizing Nuclear Waste by Innovative Gas-Cooled Reactors
By: Lomonaco, Guglielmo; Cavlina, Nikola; Romanello, V.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-18, 18 p.
مقالات
International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)
By: Aksan, Nusret; Frepoli, Cesare. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-22, 22 p.
مقالات
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation
By: Cherubini, M.; Giannotti, W.; Saha, Dilip…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-HydraulicsNeutron-Kinetics Coupled Codes : 3D S.UN.COP Seminars
By: D'Auria, Francesco; Reventos, Francesc; Frepoli, Cesare…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-16, 16 p.
مقالات
Buckling of Imperfect Thin Cylindrical Shell under Lateral Pressure
By: Lo Frano, R.; Forasassi, Giuseppe; Langenbuch, Siegfried. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-8, 8 p.
مقالات
Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor
By: Dharmaraju, N.; Rama Rao, A.; Ferreri, Juan Carlos. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications
By: Glaeser, Horst; Frepoli, Cesare. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-7, 7 p.
مقالات
Flow Stagnation under Single and Two-PhaseNatural Circulation Conditions in the APEX-CE Test Facility
By: Reyes, José N.; Cleveland, John. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-5, 5 p.
مقالات
A Statistical Methodology for Determination of Safety Systems Actuation Setpoints Based on Extreme Value Statistics
By: Novog, D. R.; Sermer, P.; Petruzzi, Alessandro. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-10, 10 p.
مقالات
Reliability Assessment of 2400 MWth Gas-Cooled Fast Reactor Natural Circulation Decay Heat Removal in Pressurized Situations
By: Bassi, C.; Marquès, M.; Cleveland, John. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-16, 16 p.
مقالات
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.
مقالات
Development Considerations of AREVA NP Inc.'s Realistic LBLOCA Analysis Methodology
By: Martin, Robert P.; O'Dell, Larry D.; Frepoli, Cesare. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-13, 13 p.
مقالات
Validation of Infinite Impulse Response Multilayer Perceptron for Modelling Nuclear Dynamics
By: Cadini, F.; Pedroni, N.; Cavlina, Nikola…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-10, 10 p.
مقالات
Deterministic Analysis of Natural Circulation Events at the Ignalina NPP
By: Uspuras, Eugenijus; Vileiniškis, Virginijus; Saha, Dilip…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-9, 9 p.
مقالات
Bootstrap and Order Statistics for Quantifying Thermal-Hydraulic Code Uncertainties in the Estimation of Safety Margins
By: Zio, Enrico; Di Maio, Francesco; Frepoli, Cesare. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-9, 9 p.
مقالات
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
By: Petruzzi, Alessandro; D'Auria, Francesco; Frepoli, Cesare. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-16, 16 p.
مقالات
An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model
By: Frepoli, Cesare; Petruzzi, Alessandro. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-15, 15 p.
مقالات
Analyses of Instability Events in the Peach Bottom-2 BWR Using Thermal-Hydraulic and 3D Neutron Kinetic Coupled Codes Technique
By: Lombardi Costa, Antonella; D'Auria, Francesco; Ambrosini, Walter…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-16, 16 p.
مقالات
Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control
By: Llopis, C.; Pretel, C.; Sol, I.…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-13, 13 p.
مقالات
BWR Stability Issues in Japan
By: Ikeda, Hideaki; Soneda, Hideo; Mizokami, Shinya…[et al.]. Science and Technology of Nuclear Installations. No. 2008 (2008), pp.1-11, 11 p.
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