Results 21 to 30 of about 6,422 (165)

Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor [PDF]

open access: yesЯдерна фізика та енергетика, 2021
The developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, the ...
Yu. Fylonych   +3 more
doaj   +1 more source

Radiation tests of products made of calcium-thermal zirconium grade СTZ-110 under operation of the VVER-440 reactor [PDF]

open access: yesЯдерна фізика та енергетика, 2020
The paper presents the results of reactor tests of fuel assemblies with cladding made of zirconium alloy grade СTZ-110 at the material testing reactor of National Research Center (NRC) "Kurchatov Institute" at Novovoronezh and Leningrad NPP under various
A.P. Mukhachev   +2 more
doaj   +1 more source

Fluid Damping in Fuel Assemblies

open access: yesVolume 4: Fluid-Structure Interaction, 2017
Damping is known to be a major parameter in the seismic design of nuclear facilities. Of special interest is the case of fuel assemblies in PWR plants, which, unlike other components, are submitted to axial flows: it has been known since the late 80s that their frequency response to lateral excitations was largely dependent on the flow velocity, and ...
Moussou, Pierre   +3 more
openaire   +2 more sources

MIXED CORE SUBCHANNEL MODEL FOR SUBCAL AND COUPLING WITH ANDREA

open access: yesActa Polytechnica CTU Proceedings, 2018
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisting of fuel assemblies with non-identical spacing grids.
Vojtěch Caha, Jiří Čížek
doaj   +1 more source

Title Investigation of the influence of various factors on the power of heat exchange by radiation

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2017
The issue of lack of knowledge of radiation heat transfer process has been repeatedly raised in various studies. Despite the fact that works on study of heat transfer by radiation covers a wide range of different industries, it should be noted the lack ...
Korolyov Alexander V.   +1 more
doaj   +1 more source

Influence of Spacer Grid Outer Strap on Fuel Assembly Thermal Hydraulic Performance

open access: yesScience and Technology of Nuclear Installations, 2014
The outer strap as a typical structure of a spacer grid enhances the mechanical strength, decreases hang-up susceptibility, and also influences thermal hydraulic performance, for example, pressure loss, mixing performance, and flow distribution.
Jingwen Yan   +4 more
doaj   +1 more source

Optimizing spent nuclear fuel cask loading for VVER-440 fuel

open access: yesNuclear Engineering and Technology
The paper explores the management of spent nuclear fuel, focusing on dual-purpose spent fuel casks used to store and transport spent nuclear fuel from VVER-440 reactors.
M. Lovecký, J. Závorka
doaj   +1 more source

Investigation of the influence of various factors on the power of heat exchange by radiation

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2017
The issue of lack of knowledge of radiation heat transfer process has been repeatedly raised in various studies. Despite the fact that works on study of heat transfer by radiation covers a wide range of different industries, it should be noted the lack ...
Олександр Вікторович Корольов   +1 more
doaj   +4 more sources

Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor

open access: yesScience and Technology of Nuclear Installations, 2015
Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective ...
Daxin Gong   +3 more
doaj   +1 more source

Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis

open access: yesNuclear Engineering and Technology
This study focused on developing and validating porous model parameters to accurately estimate the thermal behavior of spent nuclear fuel assemblies for computational fluid dynamics simulations.
Do Yun Kim   +3 more
doaj   +1 more source

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