Results 61 to 70 of about 675,221 (193)
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +2 more
doaj +1 more source
Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz +2 more
wiley +1 more source
Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis
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]
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
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
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
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
Modernized surveillance program of the VVER-1000 reactor pressure vessel metal of the Ukrainian NPP unit [PDF]
The 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
The 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
The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
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

