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International Journal of Nuclear Energy Science and Technology, ISSN 1741-6361, 2017, Volume 11, Issue 4, pp. 345 - 376
This paper discusses the calculation of the IAEA benchmark entitled In-core fuel management code package validation for WWERs (IAEA-TECDOC-847) with the... 
DONJON | VVER-1000 | VVER core follow simulation | DRAGON | VVER core calculation | VVER core analysis | VVER lattice calculation | Rooppur nuclear power plant | IAEA VVER benchmark | Cores | Boron | Depletion | Nuclear fuels | Reactors | Mathematical analysis | Inlet temperature | Feasibility studies | Benchmarks | Control rods | Mass flow
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2020, Volume 135, p. 106955
In the framework of the EU Horizon 2020 McSAFE project, a Serpent2-SUBCHANFLOW coupling has been developed with the aim at performing large-scale pin-by-pin... 
Multiphysics | SUBCHANFLOW | VVER | Serpent2 | NUCLEAR SCIENCE & TECHNOLOGY
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 ENGINEERING AND DESIGN, ISSN 0029-5493, 01/2019, Volume 341, pp. 326 - 345
After Fukushima Daiichi accident the importance of software tools that enable the NPP safety assessment for the overall sequence of severe accident processes... 
Numerical modeling | Severe accident | Nuclear power plant | Integral code | VVER | SOCRAT | NUCLEAR SCIENCE & TECHNOLOGY | RELEASE
Journal Article
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika, ISSN 0204-3327, 2019, Volume 2019, Issue 1, pp. 30 - 40
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 11/2019, Volume 353, p. 110222
This paper presents the results of calculations of the loadings that reactor main joint may experience after energetic fuel-coolant interaction in a... 
Fuel-coolant interaction | Steam explosion | Melt | Coolant | Severe accident | VVER | SOCRAT | Corium | Shock wave | STEAM EXPLOSIONS | ALUMINA | MELTS | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear fuels | Reactors | Pressure vessels | Accidents
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 11/2019, Volume 353, p. 110243
This article presents a benchmark study of a VVER 1000 core simulation of hot zero power (HZP) tests. Measured experimental data from the Temelin Unit 2... 
Serpent | Zero power criticality | NESTLE | VVER | CORE | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear power | Multiplication | Experimental data | Reactors | Computer simulation | Simulation | Benchmarks | Nuclear power plants | Nuclear reactors | Three dimensional models
Journal Article
NUCLEAR ENGINEERING AND DESIGN, ISSN 0029-5493, 10/2019, Volume 352
The problem discussed in this work concerns the estimate of integrity of the VVER reactor pressure vessel in the severe accident. In particular, the main goal... 
Severe accident | VVER | High-temperature strain | BEHAVIOR | Fracture | Ultimate strength | Strain | Young's modulus | NUCLEAR SCIENCE & TECHNOLOGY | Strength material constants | Short-time tensile test | Yield stress | Reactor pressure vessel steel 15Kh2NMFA-A | Elongation
Journal Article
Hedongli Gongcheng/Nuclear Power Engineering, ISSN 0258-0926, 10/2018, Volume 39, Issue 5, pp. 117 - 121
Journal Article
International Journal of Hydrogen Energy, ISSN 0360-3199, 08/2016, Volume 41, Issue 29, pp. 12465 - 12476
In this work, energy and exergy studies of a water-cooled water-moderated power reactor (VVER) type nuclear power plant (NPP), which is among the pressurized... 
Nuclear power | Exergy | Energy | Reactor | VVER | ELECTROCHEMISTRY | ENERGY & FUELS | CHEMISTRY, PHYSICAL | THERMOECONOMIC ANALYSIS | Thermodynamics | Nuclear energy | Analysis | Nuclear power plants | Energy efficiency | Nuclear reactors | Turbines | Pressure vessels | Nuclear reactor components | Nuclear power generation | Steam generators
Journal Article
Strojnicky Casopis, ISSN 0039-2472, 04/2017, Volume 67, Issue 1, pp. 69 - 76
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 09/2017, Volume 107, pp. 49 - 52
The proper calculation of core periphery discontinuity factors is important for accurate modeling when using an advanced nodal diffusion simulator. In cores... 
ADF | Diffusion | Hexagonal | VVER | Reflector | WER | NUCLEAR SCIENCE & TECHNOLOGY | Analysis | Algorithms
Journal Article
Energy, ISSN 0360-5442, 05/2019, Volume 175, pp. 14 - 22
Journal Article
PHYSICS OF ATOMIC NUCLEI, ISSN 1063-7788, 12/2017, Volume 80, Issue 8, pp. 1333 - 1338
The experimental procedure and the results of determination of the effective resonance neutron absorption integrals of U-238 and Gd-158 for isolated UO2-Gd2O3... 
fuel pellets | VVER-type reactor | resonance neutron absorption by U-238 | PHYSICS, NUCLEAR | urania-gadolinia fuel | PHYSICS, PARTICLES & FIELDS
Journal Article
Nuclear Physics and Atomic Energy, ISSN 1818-331X, 2014, Volume 15, Issue 1, pp. 50 - 58
Considering a VVER-1000 fuel assembly averaged fuel element (FE), based on the accepted FE cladding damage limit value, the FE cladding failure probability was... 
Cladding reliability prediction | Fuel element cladding | VVER | fuel element cladding | cladding reliability prediction
Journal Article
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