Results 1 to 10 of about 26,057 (160)

Applicability evaluation of Akaike’s Bayesian information criterion to covariance modeling in the cross-section adjustment method [PDF]

open access: yesEPJ Web of Conferences, 2023
The applicability of Akaike’s Bayesian Information Criterion (ABIC) to the covariance modeling in the cross-section adjustment method has been investigated.
Maruyama Shuhei   +2 more
doaj   +1 more source

Development and justification of fuel efficiency for subcritical installation driven by electron accelerator

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2017
The variants of design and technological features of manufacturing of fuel assemblies for the subcritical nuclear installation “Neutron Source” controlled by an electron accelerator, with rod-type fuel elements are presented.
В. С. Красноруцький   +5 more
doaj   +7 more sources

Control of the axial offset in a nuclear reactor at power maneuvering

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2014
High reliability and security of power unit are basic requirements when the power unit maneuvering mode operation. The reactor stability under disturbances both at steady load and maneuvering load embodies the guarantees of power unit safe and reliable ...
Максим Віталійович Максимов   +2 more
doaj   +7 more sources

Analysis of the Vibration Characteristics and Vibration Reduction Methods of Iron Core Reactor

open access: yesActuators, 2023
Series iron core reactors are one of the most commonly used electrical equipments in power systems, which can limit short-circuit currents and suppress harmonic waves from capacitor banks.
Zhen Wang   +4 more
doaj   +1 more source

Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core [PDF]

open access: yesNuclear Energy and Technology, 2022
Advanced pressurized water reactors are the main part of a new generation of nuclear power plant projects under development that provide cost-effective power production for various needs (Yemelyanov et al. 1982, Klimov 2002, Boyko et al.
Vyacheslav S. Kuzevanov   +1 more
doaj   +3 more sources

Reduction of activity in a research reactor waste using neutronic design [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2020
The management of waste produced in the reactor is an essential aspect of the nuclear fuel cycle. In this research, it has been tried to reduce the amount of reactor waste at the end of the cycle without substantial changes in the fuel dimension and the ...
F Mansourzadeh, F Khoshahval, J Safdari
doaj   +1 more source

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling [PDF]

open access: yesNuclear Energy and Technology, 2019
Positive effect of profiling the gas-cooled reactor core within the framework of the GT-MHR project was investigated in (Podgorny and Kuzevanov 2017, Kuzevanov and Podgorny 2017, 2018).
Vyacheslav S. Kuzevanov   +1 more
doaj   +3 more sources

Thermal-hydraulic behavior of physical quantities at critical velocities in a nuclear research reactor core channel using plate type fuel [PDF]

open access: yesNuclear Technology and Radiation Protection, 2012
The thermal-hydraulic study presented here relates to a channel of a nuclear reactor core. This channel is defined as being the space between two fuel plates where a coolant fluid flows. The flow velocity of this coolant should not generate vibrations
Sidi Ali Kamel   +2 more
doaj   +1 more source

Using software based on the Monte-Carlo method for receiving the few-group homogenized macroscopic interaction cross-section

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2017
The constant preparation issues are important for performing the few-group analysis for different states of the reactor core. Besides, the constant preparation method influences the further calculations accuracy and quality.
Віталій Володимирович Гальченко   +2 more
doaj   +7 more sources

Computational analysis of a neutron trap in the center of the WWR-K reactor core for irradiation tests of large-sized objects

open access: yesEurasian Journal of Physics and Functional Materials, 2022
Nowadays, the WWR-K research reactor is operated with low-enriched uranium fuel and a beryllium neutron reflector. Irradiation positions located in the core make it possible to irradiate objects no larger than 50 mm in size.
A. A. Shaimerdenov   +7 more
doaj   +1 more source

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