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Strojnícky casopis – Journal of Mechanical Engineering, ISSN 0039-2472, 11/2016, Volume 66, Issue 2, pp. 55 - 62
The paper is focused on CFD analyses of the coolant flow in the nuclear reactor VVER 440. The goal of the analyses is to investigate the influence of the... 
CFD simulation | VVER 440 | ANSYS CFX | thermal-hydraulics | nuclear reactor | Thermal-hydraulics | Nuclear reactor
Journal Article
Strojnicky Casopis, ISSN 0039-2472, 04/2017, Volume 67, Issue 1, pp. 69 - 76
Journal Article
Strojnícky casopis – Journal of Mechanical Engineering, ISSN 2450-5471, 04/2017, Volume 67, Issue 1, pp. 69 - 76
The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on... 
VVER 440 | ANSYS CFX | CFD analysis | thermal-hydraulics | Fuel assembly
Journal Article
Proceedings of the 13th International Scientific Conference Electric Power Engineering 2012, EPE 2012, 2012, Volume 2, pp. 1263 - 1267
Conference Proceeding
Journal of Nuclear Science and Technology, ISSN 0022-3131, 03/2000, Volume 37, Issue 1, pp. 762 - 766
Dosimetric characteristics of neutron and photon components of mixed fields have been determined at various places of the dry interim storage for spent nuclear... 
GM counter | Bonner sphere spectrometer | survey meter | neutron-photon mixed fields | pressurised-water reactor VVER 440 | CASTOR cask | interim storage | spent fuel | Pressurised-water reactor VVER 440 | Spent fuel | Survey meter | Neutron-photon mixed fields | Interim storage
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 2006, Volume 48, Issue 2, pp. 146 - 154
This paper describes validation of a computer model that has been developed for VVER 440 Nuclear Power Plant (NPP) for use with RELAP5/MOD 3.2 computer code in... 
Validation | RELAP5 | Experimental data | VVER | NPP | Thermal hydraulic code | NUCLEAR SCIENCE & TECHNOLOGY | thermal hydraulic code | experimental data | validation | Nuclear energy | Nuclear power plants | Models | Analysis
Journal Article
Transactions of the VŠB – Technical University of Ostrava, Civil Engineering Series, ISSN 1213-1962, 06/2013, Volume 13, Issue 1, pp. 9 - 19
This paper presents the new requirements to test of the safety and reliability of the NPP structures due to the last nuclear accidents in the world. The... 
VVER | Záťažové testy | probability | nonlinearity | nuclear accident | RSM | pravdepodobnosť | NPP | nelinearita | safety | bezpečnosť | jadrová nehoda | Stress tests | JE
Journal Article
Applied Mechanics and Materials, ISSN 1660-9336, 12/2012, Volume 249-250, pp. 1087 - 1098
This paper describes the reliability analysis of a concrete containment for VVER 440 under a high internal overpressure considering nonlinear behavior of... 
ANSYS | Concrete failure | Probability | Nuclear power plant VVER | Safety | RSM
Journal Article
Journal of ASTM International, ISSN 1546-962X, 04/2012, Volume 9, Issue 4, pp. 1 - 6
Analytical results of the vodo-vodyanoi energetichesky reactor- (VVER-) 440 and VVER-1000 reactor dosimetry benchmarks developed from engineering mockups at... 
Fast neutron fluence | ENDF/B-VII | Reactor dosimetry engineering benchmark | VVER | Dosimeters | Mathematical analysis | Nuclear engineering | Nuclear reactor components | Libraries | Nuclear power generation | Dosimetry | Nuclear reactors
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 08/2019, Volume 350, pp. 58 - 66
The numerical approach for the coupled damage-creep modeling of concrete biological shield, which combines the current and the past knowledge regarding the... 
Temperature | Creep | Biological shield | Neutron fluence | VVER | Concrete | Damage | Numerical analysis | Analysis | Radiation
Journal Article
Nuclear Science and Techniques, ISSN 1001-8042, 8/2019, Volume 30, Issue 8, pp. 1 - 14
There is an obvious effort to increase the burn up of used fuel assemblies in order to improve fuel utilization. A more effective operation can be realized by... 
Energy | Nuclear Physics, Heavy Ions, Hadrons | Burnable absorber | Power peaking | Nuclear Energy | Gadolinium | VVER fuel | Dysprosium | HELIOS code | IFBA | Erbium | NUCLEAR SCIENCE & TECHNOLOGY | PHYSICS, NUCLEAR
Journal Article
Key Engineering Materials, ISSN 1013-9826, 06/2017, Volume 738, pp. 261 - 272
Journal Article
Metallurgist, ISSN 0026-0894, 11/2014, Volume 58, Issue 7, pp. 694 - 699
The evolution of the design of high-power pressurized-water reactors (VVER) is discussed, key parameters of these reactors are examined, and the choice of... 
VVER | evolutionary design | Materials Science, general | structural materials | Characterization and Evaluation of Materials | Material Science | PWR | technological processes | Metallic Materials | power-generating block | service life | NPP | METALLURGY & METALLURGICAL ENGINEERING | Nuclear energy | Nuclear power plants
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 07/2012, Volume 58, pp. 76 - 88
Since 1991, the EC has been supporting the transition in Eastern European and ex-Soviet countries to market economy through the Technical Assistance to the... 
Western and Eastern TH codes application review | Severe accident analyses | VVER and RBMK reactors safety | Western TH codes transfer and training | Accident analyses | SYSTEM | NUCLEAR SCIENCE & TECHNOLOGY | THERMAL-HYDRAULIC PERFORMANCE | RBMK
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 2002, Volume 41, Issue 1, pp. 303 - 315
Rod-drop experiments performed on VVER-440 reactors are analysed using different delayed neutron data sets. It is found that for these experiments the 8 group... 
start up experiments | reactivity | pressurized water reactor (VVER) | delayed neutron data | Delayed neutron data | Reactivity | Start up experiments | Pressurized water reactor (VVER) | PARAMETERS | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Journal of ASTM International, ISSN 1546-962X, 03/2005, Volume 2, Issue 3, pp. 1 - 14
The objective of this work was firstly to categorize the data on dimensional change of the VVER fuel rods and to identify the primary variables influencing... 
Fuel rod cladding | Creep model | Irradiation-thermal creep | Irradiation growth | Zirconium alloy | Dimensional change | VVER fuel rods
Journal Article
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