Works matching IS 16876075 AND DT 2010 AND VI 2010
Results: 14
Experimental Characterization of a Passive Emergency Heat Removal Systemfor a GenIII+ Reactor.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/864709
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- Article
Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/815754
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- Article
RELAP5/MOD3.3 Best Estimate Analyses for Human Reliability Analysis.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/797193
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- Article
CATHARE Assessment of PACTEL LOCA Experiments with Accident Management.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/783204
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- Article
Fuel R&D Needs and Strategy towards a Revision of Acceptance Criteria.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/646971
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- Article
Numerical Investigation of Startup Instabilities in Parallel-Channel Natural Circulation Boiling Systems.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/574195
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- Article
Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with Different Simulation Tools.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/470794
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- Article
CATHARE Multi-1D Modeling of Coolant Mixing in VVER-1000 for RIA Analysis.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/457094
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- Article
Role of RELAP/SCDAPSIM in Nuclear Safety.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/425658
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- Article
On the Analysis and Evaluation of Direct Containement Heating with the Multidimensional Multiphase Flow Code MC3D.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/289792
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- Article
Main Results of Phase IV BEMUSE Project: Simulation of LBLOCA in an NPP.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/219294
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- Article
Application of CFD Codes in Nuclear Reactor Safety Analysis.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/198758
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- Article
Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/163279
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- Article
State of the Art of the Ignalina RBMK-1500 Safety.
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- Science & Technology of Nuclear Installations, 2010, v. 2010, p. 1, doi. 10.1155/2010/102078
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- Article