Effects of control rod movement parameters on the simulation of VVER-1200 rod ejection accidents

2024-9-12

Concentration of 95–97Mo and production of isotopically modified molybdenum in a multi-step scheme of a square cascade

2024-9-12

Development and verification of the RING 2.0 software for calculating thermal-hydraulic characteristics of fuel assemblies with annular fuel elements

2024-9-10

Methodology for forming the VVER reactor parameter requirements in cycling power reactor tests

2024-9-6

Development of an artificial neural network for a combined model of the uranium extraction process

2024-9-6

Chemical control of coolants in heavy-water systems of a PIK reactor

2024-9-5

Results of experimental testing of a hydrometallurgical technology for reprocessing spent nuclear fuel of fast neutron reactors

2024-9-5

Innovative software package for calculating the neutron-physical characteristics of RBMK-1000 reactors via the multi-group Monte Carlo method using graphic processing units (GPUs)

2024-9-5

Assessment of the state of water bodies in the territory of a decommissioned uranium mining enterprise

2024-9-5

Effects of meteorological parameters on the intensity of tritium emission from spray cooling ponds

2024-8-27

An approach to the probabilistic justification of a leak before break concept and break elimination for VVER secondary circuit pipelines

2024-8-21

Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel

2024-8-21

System for measuring the level and density of liquids in nuclear-safe devices for new spent nuclear fuel reprocessing facilities

2024-8-21

Evaluation of the effectiveness of investments in spent nuclear fuel reprocessing

2024-8-21

Estimation of the maximum mass of graphite removed during phased work on the management of RBMK-1000 resource characteristics

2024-8-21

A system for plant-wide multi-channel backup of nuclear power plant auxiliaries

2024-8-20

ANN-based mathematical model for improving the accuracy of liquid flow measurements at nuclear power plants

2024-8-14

Use of a refueling machine mast sipping system to detect leaking FAs during operational fuel cladding failure detection

2024-7-17

Approaches to slowing down the kinetics of a fast reactor as a means of enhancing its self-protection properties

2024-7-15

Study into the possibility of using two groups of accelerated preventive protection for VVER-1200 reactors

2024-7-15

Simulation of NPP cable gland leakage monitoring

2024-7-11

Accounting for the reference data correlation when determining the calculation error using the maximum likelihood method

2024-7-11

Cryogenic mesitylene-based moderator as an optimum solution for use in a DARIA compact neutron source

2024-7-11

Evaluation of technological uncertainties using the sensitivity to nuclear data

2024-7-10

A comparative analysis of the consequences of accidents at Chernobyl and Fukushima Daiichi (Japan) NPPs for agriculture and the environment

2024-7-10

Calculation of a square cascade using the bee colony algorithm

2024-7-10

Thermophysical properties of VVER uranium-gadolinium fuel pellets with 6–10 wt% of gadolinium oxide

2024-7-10

Two-cascade scheme of gas centrifuges for the purification of reprocessed uranium hexafluoride from 232, 234, 236U

2024-7-10

Control of pipeline thermal displacements using a computer vision system with a chessboard

2024-7-8

The role and position of HTGR reactor technology in the development of the Russian energy

2024-7-2

Increased sensitivity of fuel cladding failure detection

2024-6-20

Formation of design and operational databases on the reliability of equipment at Nuclear Fuel Cycle facilities

2024-6-20

Analysis of charged particle flows in the interelectrode gap of an ion-optical system

2024-6-10

Prospects for application of robotics and digitalization in integral critical experiments at compact assembly machines

2024-6-10

Development of large-scale purified inert atmosphere cells for the pyroprocessing treatment of spent nuclear fuel

2024-6-10

Debatable issues on the derivation of the separation potential for multicomponent mixtures

2024-6-10

Determination of separation power for the separation of a multicomponent isotope mixture

2024-6-10

Increasing the operational stability of a vacuum neutron tube ion source

2024-6-10

Integral experiments with a cylindrical multiplying system of metal plutonium

2024-6-10

External and internal ignition of a hydrogen-air gas mixture induced by a recombiner

2024-6-10

Determination of the dose rate from the pulse-height spectra of an airborne gamma-ray spectrometer based on an unmanned aerial vehicle

2024-6-10

Reduction of the erbium content in RBMK-1000 fuel

2024-6-10

Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading

2024-6-10

Influence of the composition and burnup of accident-tolerant fuel on the fuel component of NPP electricity cost

2024-6-10

Analysis of variation of neutronic and kinetic parameters of a Heavy Water Zero Power Reactor caused by changes in the fuel lattice pitch using MCNPX code

2024-5-2

New approaches to the separation and concentration of americium in high oxidation forms for the fractionation of high-level waste

2024-4-29

Computational analysis of a blackout accident at a decomissioned RBMK

2024-4-29

Experimental study of hydrodynamic stability limits in the system of parallel steam-generating channels

2024-4-2

Enthalpy and heat capacity of lead in a condensed state

2024-3-13

Coolant nuclid kinetics for fast reactors

2024-3-12