Results 51 to 60 of about 688 (173)
Investigation of functionals of neutron flux influencing onto VVER-440 reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2008 The calculational procedure for determination of irradiation conditions of VVER-440 reactor internals is presented. Using the developed procedure, irradiation conditions of Rovno NPP Unit1&2 VVER-440 reactor internals – baffle, basket and barrel – are ...
S. M. Pugach +3 more
doaj
Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis
Chemical Engineering &Technology, Volume 47, Issue 11, November 2024.Conventional fluids used in fission‐based water‐cooled nuclear reactors have lower heat transfer coefficients and thermal conductivity, prompting researchers to explore high‐performance fluids to enhance heat transfer and prevent core meltdown during accidents. It is crucial to investigate fluids that can improve thermal hydraulic characteristics, such
Rehan Zubair Khalid +4 more
wiley +1 more source
EPJ Web of Conferences, 2016 A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation ...
Košťál Michal +8 more
doaj +1 more source
Hydrogen Mixing Analyses for a VVER Containment [PDF]
10th International Conference on Nuclear Engineering, Volume 2, 2002 Hydrogen combustion may represent a threat to containment integrity in a VVER-440/213 plant owing to the combination of high pressure and high temperature. A study has been carried out using the GASFLOW 2.1 three-dimensional CFD code to evaluate the hydrogen distribution in the containment during a beyond design basis accident.
Sienicki, J. J., Kostka, P., Techy, Z.
openaire +1 more source
Energy Science &Engineering, Volume 12, Issue 11, Page 4894-4903, November 2024.Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants. Abstract This study investigates the impact of hybrid nanoparticles on the temperature of nuclear reactor coolant, with a focus on graphene nanoplatelet (GNP)‐based hybrid nanoparticles. Sixteen different hybrid nanofluids were analyzed, and their
Sinem Uzun, Yasin Genç, Adem Acır
wiley +1 more source
Journal of Geophysical Research: Space Physics, Volume 129, Issue 9, September 2024.Abstract In this study, we investigate the impacts of the 17 March 2013 strong geomagnetic storm on the wholly coupled Solar Wind‐Magnetosphere‐Ionosphere‐Thermosphere system‐of‐systems. Obtained from multipoint observations, our new results show (1) the solar‐wind Alfven waves propagating antisunward in the sheath region and (2) oscillating solar wind
Ildiko Horvath, Brian C. Lovell
wiley +1 more source
The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
EPJ Nuclear Sciences & Technologies, 2016 This paper shows basic features of different fuel assembly (FA) application for VVER-1000 in a closed fuel cycle based on REMIX-technology. This investigation shows how the change in the water–fuel ratio in the VVER FA affects on the fuel characteristics
Bobrov Evgenii +4 more
doaj +1 more source
Journal of Geophysical Research: Solid Earth, Volume 129, Issue 8, August 2024.Abstract Despite significant progress in studying subduction earthquake cycles, the vertical deformation is still not well understood. Here, we use a generic viscoelastic earthquake‐cycle model that has recently been validated by horizontal observations to explore the dynamics of vertical earthquake‐cycle deformation.
Shaoyang Li, Ling Chen
wiley +1 more source
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
wiley +1 more source
Science and Technology of Nuclear Installations, 2012 The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL (for
Gy. Ézsöl +3 more
doaj +1 more source