Works matching IS 16876075 AND DT 2011 AND VI 2011
Results: 38
The Best Estimate Plus Uncertainty Challenge in the Current Licensing Process of Present Reactors.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/958218
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- Article
Seismic Analysis of the Transportation Portal by the Combined Asymptotic Method.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/948457
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- Article
CFD Modeling of Wall Steam Condensation: Two-Phase Flow Approach versus Homogeneous Flow Approach.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/941239
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A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/929358
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- Article
The Argentine Approach to Radiation Safety: Its Ethical Basis.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/910718
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- Article
The Possibilities of Fission Material Reproduction Increase in Thermal Reactor with the Assemblies with a Hard Neutron Spectrum.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/897165
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- Article
CFD Analysis of Passive Autocatalytic Recombiner.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/862812
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- Article
3D Finite Elements Modelling for Design and Performance Analysis of UO<sub>2</sub> Pellets.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/843491
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Integrated Software Environment for Pressurized Thermal Shock Analysis.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/840734
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- Article
Assessment of an Isolation Condenser of an Integral Reactor in View of Uncertainties in Engineering Parameters.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/827354
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- Article
Ludwig: A Training Simulator of the Safety Operation of a CANDU Reactor.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/802410
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- Article
A Coupled Calculation Suite for Atucha II Operational Transients Analysis.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/785304
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- Article
Methods and Model Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/759847
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- Article
An Optimized Design of Single-Channel Beta-Gamma Coincidence Phoswich Detector by Geant4 Monte Carlo Simulations.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/741396
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- Article
Engineering Judgment and Natural Circulation Calculations.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/694583
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- Article
Experimental Validation of RELAP5 and TRACE5 for Licensing Studies of the Boron Injection System of Atucha II.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/693245
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- Article
Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/683147
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- Article
Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/659406
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- Article
Phenomenology of Graphite Burning in Air Ingress Accidents of HTRs.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/589747
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- Article
Calculation of the Effective Delayed Neutron Fraction by Deterministic and Monte Carlo Methods.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/584256
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- Article
CFD RecombinerModelling and Validation on the H<sub>2</sub>-Par and Kali-H<sub>2</sub> Experiments.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/574514
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- Article
Validation of Fuel-Coolant Interaction Model for Severe Accident Simulations.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/560157
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- Article
Method for the Calculation of DPA in the Reactor Pressure Vessel of Atucha II.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/534689
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- Article
Atomistic Simulation of High-Density Uranium Fuels.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/531970
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Converting Maturing Nuclear Sites to Integrated Power Production Islands.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/519538
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- Article
INVAP's Research Reactor Designs.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/490391
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- Article
Wind Turbine Blade Nondestructive Testing with a Transportable Radiography System.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/347320
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Starting Point, Keys and Milestones of a Computer Code for the Simulation of the Behaviour of a Nuclear Fuel Rod.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/326948
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- Article
Modeling of Spray System Operation under Hydrogen and Steam Emissions in NPP Containment during Severe Accident.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/284274
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Conceptual Engineering of CARA Fuel Element with Negative Void Coefficient for Atucha II.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/264235
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Nuclear Power Plant Operator Reliability Research Based on Fuzzy Math.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/262585
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Radiogenic Lead with Dominant Content of <sup>208</sup>Pb: New Coolant and Neutron Moderator for Innovative Nuclear Facilities.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/252903
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INVAP's Nuclear Calculation System.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/215363
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Nuclear Activities in Argentina, 2010.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/207625
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A New Fuel Design for Two Different HW Type Reactors.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/194650
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Simulation of the Thermal Hydraulic Processes in the Horizontal Steam Generator with the Use of the Different Interfacial Friction Correlations.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/181393
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Transparent Inflatable Column Film Dome for Nuclear Stations, Stadiums, and Cities.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/175492
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CAREM Project Status.
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- Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/140373
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- Article