Results 51 to 60 of about 399 (171)
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
A method for VVER fuel element cladding reliability prediction [PDF]
Ядерна фізика та енергетика, 2014 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 determined, thus the possibility of this reliability pre-diction by means of controlling the ...
S. M. Pelykh +2 more
doaj
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
Nuclear Engineering and Technology, 2015 The most important advantage of nanoparticles is the increased thermal conductivity coefficient and convection heat transfer coefficient so that, as a result of using a 1.5% volume concentration of nanoparticles, the thermal conductivity coefficient ...
Seyed Mohammad Mousavizadeh +2 more
doaj +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
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
Modernized surveillance program of the VVER-1000 reactor pressure vessel metal of the Ukrainian NPP unit [PDF]
Ядерна фізика та енергетикаThe surveillance program is an important source of information on the change in the properties of the metal of the water-water power reactor pressure vessel during operation.
O. V. Grytsenko +8 more
doaj +1 more source
Diagnostics of VVER-1000 core states by reactivity perturbations
Global Nuclear SafetyThe self-sustained nuclear fission chain reaction is based on the probabilistic nature of fundamental physical processes. The measure of the dynamics of these processes (state identifier) is taken to be reactivity as a special physical property of the medium or technical system.
V. Y. Shpitser, V. V. Krivin
openaire +1 more source
Validation of the code package MCPV with continuous-energy data library [PDF]
Ядерна фізика та енергетикаThe results of the validation of the code package MCPV for the calculation of radiation transport within VVER-1000 reactor type near-vessel space using a continuous-energy data library are presented.
О. M. Pugach +4 more
doaj +1 more source
Nuclear Materials and EnergyThe operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
doaj +1 more source