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

