Results 1 to 10 of about 139,532 (201)

Study on In-Service Inspection of Nuclear Fuel Assembly Failure Using Ultrasonic Plate Wave. [PDF]

open access: yesSensors (Basel), 2022
As protection for nuclear power plants is quite necessary, the nuclear fuel is sealed in zirconium alloy thin wall cladding. During service, fuel rods might be damaged caused by wall-thickness thinning, cladding corrosion and cracking, etc.
Xiao X, Zhou GZ, Wang KQ, Xi F, Zeng K.
europepmc   +2 more sources

Radiation release characterization of PWR spent fuel assemblies generated from Korean nuclear power plants [PDF]

open access: yesNuclear Technology and Radiation Protection, 2009
Spent nuclear fuel should be kept under safe management until it is disposed of permanently. Because of this, it is important to understand its radiation release characteristics.
Moon Hyun Joo
doaj   +3 more sources

Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly

open access: yesVETOR - Revista de Ciências Exatas e Engenharias, 2021
One of the challenges of future nuclear power is the development of safer and more efficient nuclear reactor designs. The AP1000 reactor based on the PWR concept of generation III + has several advantages, which can be summarized as: a modular construction, which facilitates its manufacture in series reducing the total construction time, simplification
Leonardo Acosta Martínez   +3 more
doaj   +8 more sources

Vibration Monitoring Using Fiber Optic Sensors in a Lead-Bismuth Eutectic Cooled Nuclear Fuel Assembly. [PDF]

open access: yesSensors (Basel), 2016
Excessive fuel assembly vibrations in nuclear reactor cores should be avoided in order not to compromise the lifetime of the assembly and in order to prevent the occurrence of safety hazards.
De Pauw B   +6 more
europepmc   +2 more sources

Seismic response of nuclear fuel assembly

open access: yesApplied and Computational Mechanics, 2014
The paper deals with mathematical modelling and computer simulation of the seismic response of fuel assembly components. The seismic response is investigated by numerical integration method in time domain. The seismic excitation is given by two horizontal and one vertical synthetic accelerograms at the level of the pressure vessel seating.
Hlaváč, Zdeněk, Zeman, Vladimír
openaire   +2 more sources

Modelling and modal properties of nuclear fuel assembly

open access: yesApplied and Computational Mechanics, 2011
The paper deals with the modelling and modal analysis of the hexagonal type nuclear fuel assembly. This very complicated mechanical system is created from the many beam type components shaped into spacer grids. The cyclic and central symmetry of the fuel rod package and load-bearing skeleton is advantageous for the fuel assembly decomposition into six ...
Zeman, Vladimír, Hlaváč, Zdeněk
openaire   +2 more sources

Friction and wear of elements of nuclear reactors [PDF]

open access: yesE3S Web of Conferences, 2023
Fuel elements (fuel rods) and spacer grids are the main elements of the fuel assembly of a nuclear reactor. Friction forces affect the strength of the fuel assembly at all stages of its life cycle.
Kanareykin Alexandr
doaj   +1 more source

Dynamic response of nuclear fuel assembly excited by pressure pulsations

open access: yesApplied and Computational Mechanics, 2012
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by spatial motion of the support plates in the reactor core. The support plate motion is excited by pressure pulsations generated by main circulation pumps in the coolant loops of the primary circuit of the nuclear power plant.
Zeman, Vladimír, Hlaváč, Zdeněk
openaire   +2 more sources

CFD benchmark of flat plate fuel assembly [PDF]

open access: yesMATEC Web of Conferences, 2022
Diversification of the nuclear fuel suppliers is an inseparable component of nuclear safety of power and research nuclear reactors. So far, the Czech research reactor LVR-15 has been operated with the Russian fuel IRT-4M, because there was no alternative
Hrouda Štěpán   +3 more
doaj   +1 more source

Analysis of coolant flow at the outlet of the physical model of the fuel assembly II. of the nuclear reactor VVER 440 / V213 [PDF]

open access: yesMATEC Web of Conferences, 2020
To safely and efficiently load the fuel assemblies of the VVER 440 / V 213 nuclear reactor, the relation between the temperature of the coolant at the outlet of the fuel assembly, measured by a thermocouple in the assembly’s axis, and the mean coolant ...
Mlynár Peter   +4 more
doaj   +1 more source

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