Results 1 to 10 of about 4,532 (263)

Solidification-induced nonuniformity in U–Zr–RE metallic nuclear fuel rods [PDF]

open access: yesScientific Reports
Metallic fuel is being developed for the next generation of sodium-cooled fast reactors due to its safety and fuel cycle economics through spent fuel reprocessing technology.
Seung Uk Mun   +4 more
doaj   +2 more sources

Effects of Waterlogged Fuel Rod Rupture on Adjacent Fuel Rods and Channel Box under RIA Conditions [PDF]

open access: yesJournal of Nuclear Science and Technology, 1987
This paper describes the results of in-pile experiments and analyses to study the influence of waterlogged fuel rod rupture to the adjacent fuel rods and channel box under reactivity initiated accident (RIA) conditions. A single waterlogged fuel rod surrounded by intact fuel rods m a flow shroud was irradiated by a large neutron pulse in the Nuclear ...
TANZAWA, Sadamitsu, FUJISHIRO, Toshio
exaly   +2 more sources

Criticality safety of fuel assemblies with missing fuel rods

open access: yesAnnals of Nuclear Energy
International audience ; The present work is concerned with the problem of determining the reactivity of an assembly from which an unknown number of fuel pins are removed at random locations. Because it is usually designed to be under-moderated, the reactivity of an incomplete assembly will pass by an optimum when the number and position of the missing
Benjamin Dechenaux
exaly   +3 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

Comparative Study of Spectral Regulation Range of Excess Reactivity Control in Pressurized Water Reactors Using Zirconium Displacers for Uranium and Thorium Fuel Cycles

open access: yesГлобальная ядерная безопасность, 2022
The compensation for the excess reactivity in the pressurized water reactors WWER is realized with high neutron absorber materials. The traditional excess reactivity regulation methods lead to unfeasible neutron utilization and reduce the breeding ...
A. I. Elazaka   +2 more
doaj   +1 more source

Possibility of curium as a fuel for VVER-1200 reactor

open access: yesNuclear Engineering and Technology, 2022
In this research, curium oxide (CmO2) is studied as fuel for VVER-1200 reactor to get an attention to its energy value and possibilities. For this purpose, CmO2 is used in fuel rods or integrated burnable absorber (IBA) rods with and without UO2 and then
Afroza Shelley, Mahmud Hasan Ovi
doaj   +1 more source

Fuel depletion characteristics of MA transmutation in PWR

open access: yesNuclear Materials and Energy, 2022
The minor actinide transmutation in PWR can change its fuel depletion characteristics distinctly. We simulate PWR reactor fuel depletion characteristics of minor actinide different admitting approaches on burnable poison rods for transmutation ...
Fang Liu   +6 more
doaj   +1 more source

The Problem of Modeling the Geometry of Twisted Fuel Rods with X-Type Cross Section in the Performance of Thermohydraulic Calculations

open access: yesГлобальная ядерная безопасность, 2023
For creating computational models of processes affecting the safety of nuclear facilities, in accordance with the federal rules and regulations in the field of atomic energy use, the selected modeling methods, as well as the accepted approximations and ...
Andrey M Kirkin   +4 more
doaj   +1 more source

Diameter Measurement of Fuel Rods Based on Particle Swarm Optimization With All-Parameter Adaptive Mutation Mechanism

open access: yesIEEE Access, 2020
In nuclear power plants, due to the special working environment, the status of the fuel rods will be changed by the influence of radiation. And these changes, such as diameter expansion, will cause damage to the fuel rods and even affect the safe ...
Ruirui Ji   +7 more
doaj   +1 more source

Analysis and comparison of computer programs to analyze the irradiation performance of Uranium Molybdenum monolithic fuel plates and Uranium dioxide cylindrical fuel rods in power reactors.

open access: yesBrazilian Journal of Radiation Sciences, 2021
The aim of this work is to present a comparative analysis in terms of the irradiation performance of cylindrical uranium dioxide fuel rods and monolithic uranium molybdenum fuel plates in pressurized light water reactors.
André Luiz Candido da Silva   +1 more
doaj   +1 more source

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