Tagscode VIZART 12/16/2023 computational substantiation of technology characteristics 12/16/2023 technologies of the closure of nuclear fuel cycle 12/16/2023 acoustic standing waves 12/16/2023 boron regulation 12/16/2023 neutron noise 12/16/2023 offset 12/16/2023 spectrum 12/16/2023 steam phase 12/16/2023 VVER-1200 12/16/2023 xenon oscillations 12/16/2023 CFD 12/16/2023 containment 12/16/2023 modernization 12/16/2023 NPP-2006 12/16/2023 numerical simulation 12/16/2023 operating experience 12/16/2023 steam generator 12/16/2023 ventilation 12/16/2023 AHX 12/16/2023 BN reactors 12/16/2023 hydrodynamics 12/16/2023 leaks 12/16/2023 mixingCFD 12/16/2023 pulsations 12/16/2023 sodium 12/16/2023 unevenness 12/16/2023 chemical kinetics 12/16/2023 ignition 12/16/2023 multi-step reaction 12/16/2023 productivity 12/16/2023 recombinator 12/16/2023 ampoule device 12/16/2023 energy release determination 12/16/2023 fuel rods samples 12/16/2023 instrumentation by thermocouples 12/16/2023 regular thermal mode 12/16/2023 research reactor 12/16/2023 structural materials 12/16/2023 block concept decommissioning NPP unit 12/16/2023 buildings and constructions and site NPP unit 12/16/2023 immediate dismantling 12/16/2023 NPP unit 12/16/2023 nuclear reactor 12/16/2023 radioactive wastes 12/16/2023 effective dose rate 12/16/2023 equivalent dose rate 12/16/2023 induced activity 12/16/2023 reactor core 12/16/2023 SM-3 research reactor 12/16/2023 fragmentation 99Mo 12/16/2023 highly enriched uranium 12/16/2023 low enriched uranium 12/16/2023 research reactor VVR-ts 12/16/2023 target for 99Mo production 12/16/2023 closed nuclear fuel cycle 12/16/2023 depletion of resources 12/16/2023 environmental pollution 12/16/2023 fast reactors 12/16/2023 general public 12/16/2023 nuclear power 12/16/2023 stakeholders 12/16/2023 sustainable development 12/16/2023 coolant 12/16/2023 density 12/16/2023 dynamic viscosity 12/16/2023 heat capacity 12/16/2023 potassium 12/16/2023 thermodynamic properties 12/16/2023 cooling loss 12/16/2023 experimental facility 12/16/2023 FA 12/16/2023 spent fuel pool 12/16/2023 time of start of fuel uncovering 12/16/2023 void fraction 12/16/2023 «large» leak 9/25/2023 control system for «small» leaks 9/25/2023 inter-circuit leakeness 9/25/2023 sodium coolant 9/25/2023 sodium-water steam generator 9/25/2023 steam generator protection system 9/25/2023 water leaks into sodium 9/25/2023 «practical elimination» principle 9/25/2023 design development 9/25/2023 Level 2 Probabilistic Safety Assessment 9/25/2023 nuclear power plant 9/25/2023 safety 9/25/2023 DESNA 9/25/2023 fast neutrons 9/25/2023 fuel reuse 9/25/2023 neutron physics calculation 9/25/2023 plutonium 9/25/2023 REMIX 9/25/2023 SAPPHIRE 9/25/2023 two-component nuclear power 9/25/2023 minor actinides 9/25/2023 MOX-fuel 9/25/2023 thermal reactors 9/25/2023 transmutation economics 9/25/2023 desalinated water 9/25/2023 neutral non-reactive water-chemical regime 9/25/2023 neutral oxygen water-chemical regime 9/25/2023 operational experience 9/25/2023 supercritical parameters 9/25/2023 water-chemical regime 9/25/2023 water-cooled power reactor 9/25/2023 137Cs 9/25/2023 Chernobyl accident 9/25/2023 external exposure dose 9/25/2023 internal exposure dose 9/25/2023 radioactive contamination 9/25/2023 specific activity of radionuclides in foodstuffs 9/25/2023 carbon-14 9/25/2023 food consumption 9/25/2023 inhalation 9/25/2023 internal radiation dose 9/25/2023 radiation risk 9/25/2023 enrichment 9/25/2023 frequency of overload of fuel assemblies 9/25/2023 fuel share of the cost of electricity 9/25/2023 NPP 9/25/2023 nuclear fuel burnup 9/25/2023 reactor campaign 9/25/2023 air atmosphere 9/25/2023 equilibrium constant 9/25/2023 heating 9/25/2023 radioactive graphite 9/25/2023 radionuclides 9/25/2023 thermal processes 9/25/2023 thermodynamic simulation 9/25/2023 238Pu 9/25/2023 irradiation device 9/25/2023 thermoelectric radioisotope generators 9/25/2023 VVER-1000 reactors 9/25/2023 Co-59 9/25/2023 Co-60 9/25/2023 cross section 9/25/2023 group 9/25/2023 Lu-176 9/25/2023 Lu-177g 9/25/2023 production, isotopes 9/25/2023 specific activity 9/25/2023 Yb-176 9/25/2023 BN-350 9/25/2023 characteristics of Russian-designed BN fast reactors 9/25/2023 large-scale factor 9/25/2023 multi-purpose reactor 9/25/2023 primary circuit 9/25/2023 production reactor 9/25/2023 sodium circuit flow diagram 9/25/2023 actinides 9/25/2023 fast reactor 9/25/2023 fuel cycle 9/25/2023 neutron cross-sections 9/25/2023 nuclear fuel 9/25/2023 transmutation 9/25/2023 BN-350 reactor 9/25/2023 corrosion 9/25/2023 fuel composition 9/25/2023 fuel element 9/25/2023 material test samples 9/25/2023 radiation creep 9/25/2023 swelling 9/25/2023 cooling pool 9/25/2023 dilation 9/25/2023 fuel assembly 9/25/2023 hexagonal wrapper 9/25/2023 irradiation creep 9/25/2023 steel 9/25/2023 BR-10 research reactor 9/25/2023 clinoptilolite 9/25/2023 gas-phase oxidation 9/25/2023 liquid radioactive concentrates 9/25/2023 slag 9/25/2023 slag-like compound 9/25/2023 sodium-potassium alloy 9/25/2023 solid matrix 9/25/2023 solid-phase oxidation 9/25/2023 spent alkaline liquid metal coolant 9/25/2023 delayed neutrons 6/22/2023 generation time 6/22/2023 importance function 6/22/2023 kinetic functionals 6/22/2023 MCU 6/22/2023 Monte-Carlo method 6/22/2023 neutronic calculation 6/22/2023 REMIX fuel 6/22/2023 uranium regenerate 6/22/2023 VVER 6/22/2023 fuel pellet 6/22/2023 power peaking factor 6/22/2023 specific thermal power 6/22/2023 temperature field 6/22/2023 VVER-1000 6/22/2023 Burnett equations 6/22/2023 Chapman-Enskog method 6/22/2023 coolant flow method 6/22/2023 nonlinear orthogonal transformation 6/22/2023 parabolic equation 6/22/2023 transverse leakage 6/22/2023 burnup 6/22/2023 calculation accuracy 6/22/2023 evaluated nuclear data libraries 6/22/2023 VVER reactor 6/22/2023 gas cavity 6/22/2023 helium concentration control 6/22/2023 maximum heating of fuel cladding 6/22/2023 nuclear power plants 6/22/2023 random component of measurement error 6/22/2023 temperature 6/22/2023 thermal method 6/22/2023 cask 6/22/2023 leak-tightness 6/22/2023 seal 6/22/2023 sealing assembly 6/22/2023 strain 6/22/2023 tests 6/22/2023 high-nickel steel 6/22/2023 mechanical performance 6/22/2023 reactor vessel steels 6/22/2023 structure properties 6/22/2023 temper brittleness 6/22/2023 thermal resistance 6/22/2023 ‘Warsaw’ scenario 6/22/2023 137Cs deposition densities 6/22/2023 agro-radioecological simulation model 6/22/2023 atmospheric 131I forms 6/22/2023 IAEA’s EMRAS project 6/22/2023 radioactive cloud model 6/22/2023 radioecological model verification 6/22/2023 computational support 6/22/2023 database 6/22/2023 diffusion approximation 6/22/2023 fast neutron reactor 6/22/2023 neutronic code 6/22/2023 operation support 6/22/2023 two-component nuclear power system 6/22/2023 cross-section and astrophysical factor of D + 3He → p + 4He fusion reaction 6/22/2023 effective radius approximation 6/22/2023 Lawson criterion for different D-3He fuel use scenarios 6/22/2023 thermonuclear reactions 6/22/2023 benchmark-model 6/22/2023 data assimilation 6/22/2023 integral experiment 6/22/2023 neutron constants 6/22/2023 neutronic performance 6/22/2023 process parameters 6/22/2023 237Np 6/22/2023 nuclide transformation chains 6/22/2023 economics 3/28/2023 inherently safe fast reactor 3/28/2023 levelized cost of electricity 3/28/2023 start-up with enriched uranium 3/28/2023 Brayton cycle 3/28/2023 degree of reactivity 3/28/2023 gas turbine 3/28/2023 liquid metal cooled reactors 3/28/2023 optimal ratio of speeds 3/28/2023 supercritical CO2 3/28/2023 bilinear ratios 3/28/2023 contributions of neutron reactions 3/28/2023 prompt neutron lifetime 3/28/2023 small perturbation theory 3/28/2023 Bilibino Nuclear Power Plant (BiNPP) 3/28/2023 evaporation from the water surface 3/28/2023 fuel storage pool (SP) 3/28/2023 heat exchanger (HE) 3/28/2023 isotope kinetics 3/28/2023 spent fuel assembly (SFA) 3/28/2023 thermohydraulic industry codes 3/28/2023 durability 3/28/2023 lifetime 3/28/2023 non-isothermal mixing 3/28/2023 power facility 3/28/2023 temperature pulsations 3/28/2023 thermal pulsations 3/28/2023 tracer 3/28/2023 Y-junction 3/28/2023 BN-1200 3/28/2023 MIX 3/28/2023 MOX 3/28/2023 plutonium improvement 3/28/2023 REMIX-E 3/28/2023 sodium-cooled fast reactor 3/28/2023 dosimeter 3/28/2023 exposure dose 3/28/2023 neutron energy 3/28/2023 neutron radiation 3/28/2023 phantom 3/28/2023 accidents 3/28/2023 emergency events 3/28/2023 incidents 3/28/2023 reactors 3/28/2023 statistical and system analysis 3/28/2023 technical malfunctions 3/28/2023 dry storage 3/28/2023 E110 3/28/2023 fuel rod cladding 3/28/2023 hydrides 3/28/2023 zirconium alloys 3/28/2023 analytical test 3/28/2023 approximation 3/28/2023 DRAKON code 3/28/2023 fuel pin 3/28/2023 mixed uranium-plutonium nitride fuel 3/28/2023 solution algorithm 3/28/2023 stress-strain state 3/28/2023 system of differential equations 3/28/2023 CORNER 3/28/2023 cross-verification 3/28/2023 lead-cooled fast reactor 3/28/2023 MCU-FR 3/28/2023 neutron-physical characteristics 3/28/2023 correlation model 3/28/2023 gas mixtures 3/28/2023 zirconium alloy oxidation 3/28/2023 fuel burnup 3/28/2023 nuclear concentration uncertainties 3/28/2023 nuclear concentrations 3/28/2023 variational method 3/28/2023 covariance matrices 3/28/2023 Generation IV 3/28/2023 MNPU 3/28/2023 SCALE 3/28/2023 sensitivity coefficient 3/28/2023 uncertainty 3/28/2023 breeding 12/14/2022 breeding ratio 12/14/2022 fuel production 12/14/2022 nuclide composition change 12/14/2022 protactinium pit 12/14/2022 thermal breeder reactor 12/14/2022 thorium uranium fuel cycle 12/14/2022 operational reactivity margin 12/14/2022 temperature coefficient of reactivity 12/14/2022 temperature effect of reactivity 12/14/2022 VVR-ts reactor 12/14/2022 electrical resistivity 12/14/2022 lithium coolant 12/14/2022 sound velocity 12/14/2022 surface tension 12/14/2022 thermal conductivity 12/14/2022 transport properties 12/14/2022 benchmark 12/14/2022 computational fluid dynamics 12/14/2022 computational studies 12/14/2022 CRP IAEA 12/14/2022 FlowVision 12/14/2022 heat transfer 12/14/2022 high-temperature gas-cooled reactor 12/14/2022 reactor cavity cooling system 12/14/2022 validation 12/14/2022 ISTAR software 12/14/2022 MBIR 12/14/2022 modeling 12/14/2022 molten-salt loop 12/14/2022 molten-salt reactors 12/14/2022 neutronic characteristics 12/14/2022 beyond-design-basis accident 12/14/2022 Bilibino NPP 12/14/2022 boiling water reactor 12/14/2022 EGP-6 12/14/2022 hydrogen explosion safety 12/14/2022 KUPOL-M code 12/14/2022 radiolysis products 12/14/2022 radiolytic hydrogen 12/14/2022 electrical resistance 12/14/2022 gravity measurements 12/14/2022 internal friction 12/14/2022 interstitial atoms 12/14/2022 neutron irradiation 12/14/2022 phase transformations 12/14/2022 radiation defects 12/14/2022 radiation-induced segregation 12/14/2022 vacancies 12/14/2022 lead 12/14/2022 lead-bismuth 12/14/2022 measurement error 12/14/2022 oxygen activity sensors in liquid metals 12/14/2022 oxygen thermodynamic activity 12/14/2022 reference installation 12/14/2022 steam-hydrogen gas mixtures 12/14/2022 verification 12/14/2022 charge in a fission chamber pulse 12/14/2022 fission chamber 12/14/2022 fission fragment 12/14/2022 ionization 12/14/2022 neutron 12/14/2022 neutron detection 12/14/2022 radiation density measurement 12/14/2022 reactor target 12/14/2022 transmission spectrum 12/14/2022 X-ray source 12/14/2022 classification 12/14/2022 cloud computing 12/14/2022 knowledge database 12/14/2022 machine learning 12/14/2022 semantic annotation 12/14/2022 semantic web 12/14/2022 delayed neutron multiplication factor 12/14/2022 nuclear reactor dynamics 12/14/2022 alkali liquid metals 9/23/2022 codes 9/23/2022 control of impurity content 9/23/2022 impurities 9/23/2022 mass transport 9/23/2022 purification 9/23/2022 thermonuclear reactors 9/23/2022 thermophysical and physicochemical processes and characteristics 9/23/2022 recompression thermodynamic cycle 9/23/2022 dynamics 9/23/2022 feedbacks 9/23/2022 pressurized water cooled water moderated reactor 9/23/2022 simulation 9/23/2022 multiple use of fuel 9/23/2022 saving natural resources 9/23/2022 thorium 9/23/2022 uranium-thorium fuel cycle 9/23/2022 control and diagnostic control system 9/23/2022 diagnostic information 9/23/2022 free objects control system 9/23/2022 software and hardware complex 9/23/2022 technical diagnostics system 9/23/2022 vibration control system 9/23/2022 Bilibinо NPP 9/23/2022 similarity theory 9/23/2022 tank-type boiling water reactor 9/23/2022 VK-50 9/23/2022 fuel cladding failure detection systems 9/23/2022 LMFBR 9/23/2022 measurement of volumetric activity of inert gases 9/23/2022 aging processes 9/23/2022 damage accumulation 9/23/2022 failure rate 9/23/2022 lifetime management 9/23/2022 residual lifetime 9/23/2022 cladding 9/23/2022 fuel assembly (FA) 9/23/2022 long-term storage 9/23/2022 mechanical properties 9/23/2022 metallographic studies 9/23/2022 nickel 9/23/2022 radiation resistance 9/23/2022 service properties 9/23/2022 steels of internals 9/23/2022 steels of RPV 9/23/2022 structural characteristics 9/23/2022 Am 9/23/2022 biological hazard 9/23/2022 burning 9/23/2022 Cm 9/23/2022 fast neutron nuclear reactor 9/23/2022 neutron spectrum 9/23/2022 Np 9/23/2022 radiotoxicity 9/23/2022 SNF 9/23/2022 SNF storage 9/23/2022 transmutation, minor actinides 9/23/2022 curvilinear boundaries 9/23/2022 grids 9/23/2022 transport equation 9/23/2022 complimentary geometry 9/23/2022 model 9/23/2022 radiation hygiene 9/23/2022 agrarian agricultural radiation technology 9/23/2022 bachelor’s degree course 9/23/2022 development of human resources 9/23/2022 export of education 9/23/2022 master’s degree course 9/23/2022 practice-oriented approach 9/23/2022 resource center 9/23/2022 vocational training 9/23/2022 efficiency 6/20/2022 energy model 6/20/2022 environmental constraints 6/20/2022 forecast 6/20/2022 class of events 6/20/2022 main circulation circuit 6/20/2022 neural network 6/20/2022 shock event 6/20/2022 system for detecting loose and loosely attached objects 6/20/2022 technical diagnostics systems 6/20/2022 VVER-440 6/20/2022 AES-2006 6/20/2022 operation 6/20/2022 purge 6/20/2022 re-routing 6/20/2022 regenerative heat exchanger 6/20/2022 RU V-392M 6/20/2022 strapping 6/20/2022 automatic power regulator (APR) 6/20/2022 axial offset (AO) 6/20/2022 offset-phase diagram 6/20/2022 suppression algorithm 6/20/2022 water exchange 6/20/2022 core 6/20/2022 data bases 6/20/2022 designcodes 6/20/2022 emergency situations 6/20/2022 experiment 6/20/2022 pressure 6/20/2022 reactor vessel 6/20/2022 thermal hydraulics 6/20/2022 velocity 6/20/2022 computer simulation 6/20/2022 decommissioning 6/20/2022 filter container 6/20/2022 hydraulic resistance 6/20/2022 ion-selective treatment 6/20/2022 liquid radioactive waste 6/20/2022 optimization of radiation protection 6/20/2022 porosity 6/20/2022 sorbents 6/20/2022 dose rate 6/20/2022 geometry splitting with Russian roulette 6/20/2022 MAGIC (Method of Automatic Generation of Importances by Calculation) method 6/20/2022 spent removable part of reactor 6/20/2022 concentration 6/20/2022 Gibbs thermodynamic potential 6/20/2022 liquid metal coolant 6/20/2022 magnesium 6/20/2022 reaction constant 6/20/2022 saturation concentration 6/20/2022 sodium, fast reactor 6/20/2022 soluble getter 6/20/2022 BR-10 RR 6/20/2022 gas-phase neutralization 6/20/2022 GETTER module 6/20/2022 liquid metal chromatography 6/20/2022 LUIZA-RW module 6/20/2022 MAGMA-SPO module 6/20/2022 magnesium sorbent 6/20/2022 technologies for processing of alkaline liquid metal coolant 6/20/2022 co-precipitation 6/20/2022 drain water 6/20/2022 membrane separation 6/20/2022 processing 6/20/2022 effectiveness of involvement of depleted uranium in production process 6/20/2022 enriched uranium products cost 6/20/2022 multi-threaded enrichment production 6/20/2022 separative work unit 6/20/2022 burnup calculations 6/20/2022 reactor plant 6/20/2022 uncertainties in nuclear data 6/20/2022 uncertainties in nuclide nuclear concentrations 6/20/2022 BPSD 6/20/2022 neutron-physical parameters 6/20/2022 nuclear energy 6/20/2022 nuclear energy system 6/20/2022 nuclear fuel cycle 6/20/2022 nuclear technologies 6/20/2022 scenario analysis 6/20/2022 software tool 6/20/2022 technical and economic modelling 6/20/2022 critical mass 6/20/2022 hard gamma radiation 6/20/2022 heat generation 6/20/2022 integral indicator of proliferation protection of the material 6/20/2022 proliferation protection of uranium 6/20/2022 radiolysis of uranium hexafluoride 6/20/2022 source of neutrons 6/20/2022 effective delayed neutron fraction 6/20/2022 lead-bismuth coolant 1/20/2022 reactor 1/20/2022 Arctic 1/20/2022 energy storage devices 1/20/2022 hydrogen 1/20/2022 new technological platform 1/20/2022 small modular reactor 1/20/2022 synthetic carbon-free fuel 1/20/2022 99Mo production 1/20/2022 enrichment reduction 1/20/2022 MAK-2 research channel 1/20/2022 power density 1/20/2022 thermohydraulic calculation 1/20/2022 absorption cross-section 1/20/2022 ageing and model refueling 1/20/2022 deflection 1/20/2022 infinite multiplication factor 1/20/2022 Samarium 1/20/2022 SERPENT 1/20/2022 Xenon 1/20/2022 heat sink function 1/20/2022 real time 1/20/2022 thermal conductivity equation 1/20/2022 form change 1/20/2022 natural convection 1/20/2022 ultrasonic technique 1/20/2022 coolant level 1/20/2022 level measurement 1/20/2022 level measurement methods 1/20/2022 cliff edge effects 1/20/2022 accelerator mass spectrometer 1/20/2022 pine tree rings 1/20/2022 design schemes 1/20/2022 duration of the campaign 1/20/2022 steam chamber 1/20/2022 thermionic reactor-converter 1/20/2022 (α, n)-reaction 1/20/2022 dosimetry 1/20/2022 low-enriched uranium nuclear fuel 1/20/2022 TheIVG.1M research reactor 1/20/2022 chain of nuclide transformations of uranium-232 1/20/2022 hard γ-radiation 1/20/2022 incubator 1/20/2022 innovation 1/20/2022 innovation science and technology center 1/20/2022 personnel training 1/20/2022 research University 1/20/2022 science city 1/20/2022 silicon valley 1/20/2022 Skolkovo 1/20/2022 technological valley 1/20/2022 technopark 1/20/2022 «V» Laboratory 1/20/2022 atoms for peace history 1/20/2022 nuclear power train 1/20/2022 power self-propelled power plant 1/20/2022 the first mobile low-power nuclear power plant 1/20/2022 TPP-3 1/20/2022 transportable land-based nuclear-fueled power plant 1/20/2022 water-moderated reactor 1/20/2022 accident 12/08/2021 polonium 12/08/2021 exposure doses 12/08/2021 man-made contamination 12/08/2021 radiation safety 12/08/2021 radiological and environmental monitoring 12/08/2021 hybrid «fusion-fission» reactor facility 12/08/2021 neutronic research 12/08/2021 plasma generator of D-T-neutrons 12/08/2021 radioactivity 12/08/2021 spent fuel 12/08/2021 spent fuel storage 12/08/2021 3LiCl-2KCl 12/08/2021 anode sludge 12/08/2021 electrolyser 12/08/2021 filter element 12/08/2021 intermetallid 12/08/2021 PFC 12/08/2021 FACT-BR 12/08/2021 lead coolant 12/08/2021 KL-15 transportation container 12/08/2021 maximum permissible activity 12/08/2021 molybdenum-99 12/08/2021 molybdenum-technetium generators 12/08/2021 packaging kits 12/08/2021 radiation safety during transportation 12/08/2021 technetium-99m 12/08/2021 fuel rod 12/08/2021 loss of cooling 12/08/2021 spent fuel pond 12/08/2021 control algorithm 12/08/2021 mathematical model 12/08/2021 nonlinear automatic control system 12/08/2021 power turbine 12/08/2021 stability of control process 12/08/2021 acoustic standing wave 12/08/2021 autospectral power density 12/08/2021 cross-spectral power density 12/08/2021 pressure pulsation detector 12/08/2021 reactor coolant pump 12/08/2021 technical diagnostics 12/08/2021 fluoride glass 12/08/2021 gamma detectors 12/08/2021 intense neutron field 12/08/2021 ionization chamber 12/08/2021 neutron detectors 12/08/2021 nuclear-optical converter 12/08/2021 scintillator 12/08/2021 delayed criticality 12/08/2021 prompt criticality 12/08/2021 additional income 9/23/2021 fast and thermal reactors 9/23/2021 levelized unit fuel cost 9/23/2021 nuclear fuel cycle closure 9/23/2021 plutonium production 9/23/2021 technical and economic performance 9/23/2021 experimental channel 9/23/2021 target for the production of Mo-99 9/23/2021 VVR-c reactor 9/23/2021 flow instabilities 9/23/2021 numerical models 9/23/2021 supercritical water 9/23/2021 boiling margin 9/23/2021 critical heat flow 9/23/2021 departure from nucleate boiling 9/23/2021 highly efficient cooling technology 9/23/2021 americium 9/23/2021 closed fuel cycle 9/23/2021 curium 9/23/2021 neptunium 9/23/2021 automated system 9/23/2021 diagnosing 9/23/2021 electrically-actuated valves 9/23/2021 neural networks 9/23/2021 NPP safety 9/23/2021 pipelines 9/23/2021 segmentation 9/23/2021 BREST 9/23/2021 bubbling up 9/23/2021 cladding defect 9/23/2021 degassing 9/23/2021 diffusion 9/23/2021 fission products 9/23/2021 fuel-element cladding tightness monitoring 9/23/2021 inert radioactive gases 9/23/2021 two-phase flows 9/23/2021 fuel pellets 9/23/2021 pore agent 9/23/2021 resintering 9/23/2021 thermal stability 9/23/2021 U-Gd fuel rod 9/23/2021 uranium-gadolinium fuel 9/23/2021 capital and operating costs 9/23/2021 investment efficiency criteria 9/23/2021 Northern Sea Route (NSR) 9/23/2021 nuclear icebreakers 9/23/2021 revenues 9/23/2021 ship escort tariffs 9/23/2021 competitiveness 9/23/2021 energy generating company 9/23/2021 normative and evaluative model 9/23/2021 electromagnetic valve 9/23/2021 purge collector 9/23/2021 steam generator collector pocket 9/23/2021 fast neutron reactors 9/23/2021 natural circulation 9/23/2021 thermohydraulic simulation 9/23/2021 carbon ions 9/23/2021 cervical cancer cells 9/23/2021 chemotherapy 9/23/2021 HeLa 9/23/2021 particle therapy 9/23/2021 alarm 6/15/2021 functions 6/15/2021 information 6/15/2021 interactive procedure 6/15/2021 operator information support system 6/15/2021 dynamic stability 6/15/2021 electric feeding pump 6/15/2021 power unit simulation 6/15/2021 BN-type reactor 6/15/2021 burnable absorber 6/15/2021 criticality equation 6/15/2021 eigenfunctions expansion 6/15/2021 neutron field stability 6/15/2021 neutron flux density 6/15/2021 optimal profiling 6/15/2021 spatial kinetic 6/15/2021 neutron coincidence method 6/15/2021 prompt neutron multiplication factor 6/15/2021 Rossi alpha method 6/15/2021 spatial isotope correlation factor 6/15/2021 close fuel cycle 6/15/2021 double cascade 6/15/2021 radiolysis 6/15/2021 regenerated uranium 6/15/2021 uranium hexafluoride 6/15/2021 AM (AMB) reactor 6/15/2021 damaged SNF 6/15/2021 fire and explosion safety 6/15/2021 methane 6/15/2021 storage in wate 6/15/2021 aircraft crash 6/15/2021 damping structures 6/15/2021 hangar-type storage 6/15/2021 impact of the flying body 6/15/2021 protective shell 6/15/2021 radiation package 6/15/2021 safety of nuclear fuel cycle facilities 6/15/2021 temporary storage 6/15/2021 BARS-6 pulse reactor 6/15/2021 Fricke ferrous sulphate dosimeter 6/15/2021 gamma radiation 6/15/2021 ultra-high dose rate 6/15/2021 backpressure flowing 6/15/2021 gaseous oxygen 6/15/2021 Gibbs energy 6/15/2021 hydrogen purification from slags 6/15/2021 lead oxide activity 6/15/2021 lead-bismuth eutectic 6/15/2021 lead-containing coolant 6/15/2021 oxidation pattern 6/15/2021 slags based on lead oxides 6/15/2021 cost and construction time 6/15/2021 digitalization of NPP design and construction 6/15/2021 investment efficiency 6/15/2021 catalytically closed internal fuel cycle 6/15/2021 control of thermal neutron flux 6/15/2021 radial magnetic dynamic (RMHD) generator 6/15/2021 selective separation effect of thermal neutrons 6/15/2021 thermonuclear reactor 6/15/2021 convolutional neural network 6/15/2021 time series segmentation 6/15/2021 MAVT 3/18/2021 MESSAGE-NES 3/18/2021 Chexal-Horowitz Flow-Accelerated Corrosion Model 3/18/2021 corrosion rate estimation 3/18/2021 erosion-corrosion wear 3/18/2021 main challenges of the present day 3/18/2021 National Priority Projects 3/18/2021 pipeline wall thinning 3/18/2021 circulating water supply system 3/18/2021 Nalko 1392 3/18/2021 scale formation 3/18/2021 scale inhibitor 3/18/2021 aluminum 3/18/2021 aluminum oxide 3/18/2021 boric acid 3/18/2021 hydrogen and radiation safety of nuclear reactors 3/18/2021 hydroheterogeneous composition 3/18/2021 lithium hydroxide 3/18/2021 potassium hydroxide 3/18/2021 sodium hydroxide 3/18/2021 water 3/18/2021 boron 3/18/2021 control and protection system 3/18/2021 micro-fuel 3/18/2021 plasma neutron source 3/18/2021 thorium hybrid reactor 3/18/2021 ABBN 3/18/2021 BFS 3/18/2021 database ща integral experiments 3/18/2021 ENDF 3/18/2021 integral experiments 3/18/2021 JEFF 3/18/2021 JENDL 3/18/2021 ROSFOND 3/18/2021 ANSYS FLUENT 3/18/2021 laminarity 3/18/2021 turbulence 3/18/2021 cesium 3/18/2021 clays 3/18/2021 sorption 3/18/2021 strontium 3/18/2021 closed internal fuel cycle 3/18/2021 deep fuel burn-up 3/18/2021 neutron flux control 3/18/2021 SFC – slowing-focusing structure 3/18/2021 thermal neutron separation effect 3/18/2021 heavy accidents 3/18/2021 self-protection 3/18/2021 inhomogeneities in radiation protection 3/18/2021 leakage albedo 3/18/2021 acoustic measurement 3/18/2021 gamma irradiation 3/18/2021 optical properties 3/18/2021 quartz glass 3/18/2021 radiation hardening 3/18/2021 teaching methods 3/18/2021 Arctic region 11/19/2020 development forecast 11/19/2020 distributed generation 11/19/2020 isolation power system 11/19/2020 Low-Power Nuclear Power Plant 11/19/2020 mathematical modeling 11/19/2020 sea areas 11/19/2020 spent fuel storage pool 11/19/2020 spent nuclear fuel 11/19/2020 temperature conditions 11/19/2020 coolant fluid dynamics 11/19/2020 interassembly interaction 11/19/2020 mixing grids 11/19/2020 spacer grids 11/19/2020 algorithms 11/19/2020 decision-making 11/19/2020 design solutions 11/19/2020 I&C 11/19/2020 monitoring 11/19/2020 OISS 11/19/2020 optimization 11/19/2020 power unit model 11/19/2020 technological process 11/19/2020 burn-up depth 11/19/2020 cladding integrity 11/19/2020 combined dimensionless parameter 11/19/2020 effective life 11/19/2020 energy resource 11/19/2020 fuel matrix 11/19/2020 swelling compensator 11/19/2020 uranium dioxide 11/19/2020 boiling point 11/19/2020 critical heat flux 11/19/2020 heat supply and removal 11/19/2020 results of experimental studies 11/19/2020 working area 11/19/2020 integral layout 11/19/2020 inter-wrapper space 11/19/2020 liquid metal cooled reactor 11/19/2020 LMS 11/19/2020 methodological approach 11/19/2020 reactor cooldown 11/19/2020 acoustic sensors 11/19/2020 algorithm 11/19/2020 background noise 11/19/2020 filtration 11/19/2020 humidity sensors 11/19/2020 leak analysis 11/19/2020 NPP gas and aerosol emissions 11/19/2020 turbulent diffusion modeling 11/19/2020 131I in vegetation 11/19/2020 137Cs fallout 11/19/2020 agro-radioecological model 11/19/2020 atmosphere 11/19/2020 estimated data 11/19/2020 instrumental data 11/19/2020 mutually consistent database 11/19/2020 rainfall 11/19/2020 economy 11/19/2020 natural real indicators 11/19/2020 natural uranium 11/19/2020 recycled uranium 11/19/2020 separate work units 11/19/2020 finite element method 11/19/2020 HPC cluster 11/19/2020 MPI 11/19/2020 ODETTA software 11/19/2020 parallel programming 11/19/2020 efficient SNF and RW management 9/16/2020 export potential 9/16/2020 data filtration 9/16/2020 erosion-corrosion rate estimation 9/16/2020 Keller coefficient 9/16/2020 lifetime estimation 9/16/2020 repeated control data 9/16/2020 axial offset 9/16/2020 flexible (load tracing) operating modes 9/16/2020 reactor stability 9/16/2020 VVER-1000 (1200) 9/16/2020 asymptotic runaway 9/16/2020 kinetics 9/16/2020 nuclear chain reaction 9/16/2020 reflectors based on natural lead and lead-208 9/16/2020 transient process 9/16/2020 VVER and CANDU thermal reactors 9/16/2020 coolant activity 9/16/2020 fuel carryover 9/16/2020 fuel failure 9/16/2020 iodine radionuclides 9/16/2020 methodology 9/16/2020 erbium 9/16/2020 GETERA 9/16/2020 liquid excessive reactivity compensation system 9/16/2020 liquid radioactive waste (LRW) 9/16/2020 reactivity margin 9/16/2020 equilibrium cycle 9/16/2020 excess reactivity 9/16/2020 nitride fuel 9/16/2020 heat-producing materials 9/16/2020 mixed convection 9/16/2020 storage facility 9/16/2020 thermal safety 9/16/2020 SCWR reactor 9/16/2020 supercritical coolant parameters 9/16/2020 angular velocity vector 9/16/2020 breakdown of fuel elements 9/16/2020 helical vortex cord 9/16/2020 inertial wave vector 9/16/2020 pressure fluctuation amplitude 9/16/2020 shear power 9/16/2020 vibration period and frequency 9/16/2020 alloys 9/16/2020 annealing 9/16/2020 impurity atoms 9/16/2020 iron 9/16/2020 nitrogen 9/16/2020 oxygen 9/16/2020 vanadium 9/16/2020 16Cr-19Ni class steel 9/16/2020 average radiation-induced swelling rate 9/16/2020 MCU-BR 9/16/2020 MMK-RF 9/16/2020 MMK-ROCOCO 9/16/2020 Monte Carlo codes 9/16/2020 anomalies in the operation of reactor equipment 9/16/2020 the system of technical diagnostics of NPP equipment 9/16/2020 time series 9/16/2020 elliptical mirror 9/16/2020 method and apparatus for investigation thermal neutron beams 9/16/2020 neutron transmutation 9/16/2020 silicon 9/16/2020 thermal neutron beams 9/16/2020 thermal neutrons 9/16/2020 Geant4 9/16/2020 mathematical simulation 9/16/2020 neutron generator 9/16/2020 cooling towers 7/09/2020 engineering support 7/09/2020 Novovoronezh NPP-2 7/09/2020 service water supply 7/09/2020 upgrade 7/09/2020 D-D neutron plasma pulse periodic generator 7/09/2020 fission wave 7/09/2020 fusion- fission hybrid reactor 7/09/2020 boric regulation 7/09/2020 excessive reactivity 7/09/2020 reactivity 7/09/2020 reactivity coefficients 7/09/2020 spectral regulation 7/09/2020 water displacers 7/09/2020 equilibrium pressure 7/09/2020 metal-oxide system 7/09/2020 oxidation potential 7/09/2020 state diagram 7/09/2020 electrochemical potential 7/09/2020 galvanic effect 7/09/2020 oxide film 7/09/2020 zirconium alloy 7/09/2020 heavy liquid metal coolant 7/09/2020 impeller blades 7/09/2020 impellers 7/09/2020 main circulation pump 7/09/2020 pump feed and discharge 7/09/2020 buildings and structures 7/09/2020 decommissioning option 7/09/2020 dismantling of components 7/09/2020 in-situ disposal 7/09/2020 radioactive waste 7/09/2020 atmospheric air and precipitation 7/09/2020 dust 7/09/2020 People’s Republic of Bangladesh 7/09/2020 radioecological monitoring 7/09/2020 radon 7/09/2020 atmospheric release 7/09/2020 geoinformation system 7/09/2020 prediction 7/09/2020 radiation situation 7/09/2020 support of decision-making 7/09/2020 burn-up calculations 7/09/2020 reactor facility 7/09/2020 uncertainties in nuclear concentrations of nuclides 7/09/2020 diagnostics 7/09/2020 diagnostics of heat-transfer transients 7/09/2020 digital twin 7/09/2020 thermohydraulic flow loop 7/09/2020 MVP 7/09/2020 nuclear fuel extraction 7/09/2020 nuclear safety 7/09/2020 Daphniamagna 7/09/2020 heart rate 7/09/2020 long-term radiation-induced effect 7/09/2020 method of interferometry of living systems 7/09/2020 radioecology 7/09/2020 activation detectors 7/09/2020 geometric factor 7/09/2020 information model 3/19/2020 NPP operation experience 3/19/2020 personnel reliability 3/19/2020 beam ports 3/19/2020 IRT-T 3/19/2020 NCT 3/19/2020 neutron capture therapy 3/19/2020 radiation treatment 3/19/2020 fuel temperature coefficient 3/19/2020 light water reactor 3/19/2020 moderator temperature coefficient 3/19/2020 protactinium 3/19/2020 ultra-high fuel burn-up 3/19/2020 burn-up 3/19/2020 fuel utilization 3/19/2020 nuclear burning wave 3/19/2020 nuclear concentration of nuclides 3/19/2020 reactor life 3/19/2020 traveling wave reactor 3/19/2020 neutron flux 3/19/2020 reflector 3/19/2020 SCALE software package 3/19/2020 characteristic equation 3/19/2020 environment 3/19/2020 Fourier method 3/19/2020 geometrical parameter 3/19/2020 heat sources 3/19/2020 k-layer plate and cylinder 3/19/2020 kernel of transformation 3/19/2020 method of finite integral transformations 3/19/2020 two-dimensional non-stationary heat conduction problem 3/19/2020 cross#cycling 3/19/2020 mixed fuel 3/19/2020 NFC 3/19/2020 recycling 3/19/2020 uranium-plutonium fuel 3/19/2020 elastic modulus 3/19/2020 molybdenum 3/19/2020 niobium 3/19/2020 refractory metals 3/19/2020 rhenium 3/19/2020 tungsten 3/19/2020 circulation loop 3/19/2020 control 3/19/2020 heavy coolant 3/19/2020 oxygen!ion electrolyte 3/19/2020 mass content of impurity 3/19/2020 mass transfer 3/19/2020 oxygen activity sensor 3/19/2020 structural steel 3/19/2020 thermodynamic activity 3/19/2020 local sound velocity 3/19/2020 regression 3/19/2020 viscosity 3/19/2020 argon cooling 3/19/2020 cold trap 3/19/2020 computation code 3/19/2020 sodium cooling 3/19/2020 heat-exchange 3/19/2020 identification 3/19/2020 Petri nets 3/19/2020 steam void 3/19/2020 current sources with radioactive isotopes (CSRI) 3/19/2020 radiation-induced electric charge 3/19/2020 supercapacitor 3/19/2020 decommissioning of nuclear and radiation hazardous objects 3/19/2020 education and training of personnel for nuclear decommissioning 3/19/2020 final stages of life cycle of nuclear facilities 3/19/2020 radiation protection optimization 3/19/2020 advanced analytics 12/05/2019 data analysis 12/05/2019 fault detection 12/05/2019 acoustic wave 12/05/2019 diagnostics of NPPs 12/05/2019 impact localization 12/05/2019 Loose Part Monitoring System (LPMS) 12/05/2019 VVER reactor plant 12/05/2019 gamma source 12/05/2019 neutron source 12/05/2019 radiation protection calculation 12/05/2019 spent fuel transfer cask 12/05/2019 fast reactor of small capacity 12/05/2019 hard neutron spectrum 12/05/2019 incineration of low fissile isotopes 12/05/2019 lead-208 coolant 12/05/2019 metallic Pu-Am-Np-Zr fuel 12/05/2019 BNAB-RF 12/05/2019 effective neutron multiplication factor 12/05/2019 Monte Carlo 12/05/2019 spectral indices 12/05/2019 radiogenic lead 12/05/2019 reactivity accident 12/05/2019 emergency release 12/05/2019 frequency 12/05/2019 maintenance 12/05/2019 nuclear fuel damage 12/05/2019 probability 12/05/2019 risk 12/05/2019 safety level 12/05/2019 technological regulation 12/05/2019 circuit design 12/05/2019 instrumental function 12/05/2019 reactimeter 12/05/2019 variant analysis 12/05/2019 conservative approach 12/05/2019 NPP Mochovce 12/05/2019 parametric analyses 12/05/2019 Serpent 2 12/05/2019 spent fuel storage pool (SFSP) 12/05/2019 austenitic steel 12/05/2019 elasticity characteristics 12/05/2019 internals 12/05/2019 irradiation-induced swelling 12/05/2019 porosity characteristics 12/05/2019 (γ, n) reaction 12/05/2019 100Mo production 12/05/2019 beam modernization 12/05/2019 carbothermal synthesis 12/05/2019 CFD model 12/05/2019 compact clinical installation 12/05/2019 electron accelerator 12/05/2019 furnace 12/05/2019 grid model 12/05/2019 MNUP fuel 12/05/2019 photoneutrons 12/05/2019 radioisotopes production 12/05/2019 SolidWorks Flow Simulation 12/05/2019 limits and conditions of operation 9/30/2019 management optimization 9/30/2019 multi-user program 9/30/2019 start-up operations 9/30/2019 technical condition analysis 9/30/2019 air-water mist 9/30/2019 heat exchange intensification 9/30/2019 particulate cooling 9/30/2019 water concentration 9/30/2019 critical fluence 9/30/2019 damaging neutrons 9/30/2019 graphite lifespan 9/30/2019 GT-MHR 9/30/2019 HTGR 9/30/2019 mode 9/30/2019 reactivity coefficient 9/30/2019 reactor coolant pump (RCP) 9/30/2019 reactor plant power 9/30/2019 reactor-grade graphite 9/30/2019 safety margin 9/30/2019 scram 9/30/2019 heat sink 9/30/2019 porous body 9/30/2019 reactor core profiling 9/30/2019 transient conditions 9/30/2019 IRT 9/30/2019 long-term campaign 9/30/2019 low-enriched fuel 9/30/2019 VVR 9/30/2019 cascade 9/30/2019 filling 9/30/2019 gas centrifuge 9/30/2019 germanium 9/30/2019 isotope 9/30/2019 non-stationary process 9/30/2019 separation 9/30/2019 stage 9/30/2019 Elcometer 7061 Marsurf PS1 roughness meter 9/30/2019 life extension 9/30/2019 metal corrosion 9/30/2019 operating conditions 9/30/2019 parent metal 9/30/2019 preventive maintenance 9/30/2019 surface roughness 9/30/2019 fabrication technology 9/30/2019 grain size 9/30/2019 high-temperature embrittlement 9/30/2019 swelling rate 9/30/2019 affine time transformation method 9/30/2019 bismuth oxide 9/30/2019 equation of nucleation and growth model 9/30/2019 heavy liquid metal coolants 9/30/2019 hydrogen afterburner 9/30/2019 hydrogen purification of HLMC 9/30/2019 reaction kinetics 9/30/2019 thermoconductometric analysis 9/30/2019 tritium 9/30/2019 Yerofeev’s equation 9/30/2019 aquatic environment 9/30/2019 artificial defect 9/30/2019 corrosion tests 9/30/2019 fission product release 9/30/2019 fuel material 9/30/2019 fuel-element claddings 9/30/2019 metallography 9/30/2019 γ-dose rate 9/30/2019 experiment simulation 9/30/2019 Iron 88 benchmark 9/30/2019 multigroup cross sections 9/30/2019 parallel computations 9/30/2019 reactor rates 9/30/2019 tetrahedral grids 9/30/2019 electrochemical deactivation 9/30/2019 irradiated graphite 9/30/2019 leaching 9/30/2019 centralized nuclear fuel cycle 6/24/2019 dual component nuclear energy system 6/24/2019 industrial power complex from the supplier (Rosatom) 6/24/2019 fission fragments 6/24/2019 laser 6/24/2019 neutrons 6/24/2019 nuclear pumping 6/24/2019 optical quantum amplifier with nuclear pumping 6/24/2019 acceleratordriven system 6/24/2019 leadbismuth 6/24/2019 superconducting linear accelerator 6/24/2019 nuclear fuel evolution 6/24/2019 system analysis of nuclear power 6/24/2019 automated power controller (APC) 6/24/2019 offset-power phase diagram 6/24/2019 CCP efficiency 6/24/2019 condensate path (CP) 6/24/2019 deaerator (D) 6/24/2019 feed water (FW) 6/24/2019 feedwater pump (FWP) 6/24/2019 gas heater (GH) 6/24/2019 high pressure cylinder (HPC) 6/24/2019 high pressure drum-separator (HPDS) 6/24/2019 low pressure cylinder (LPC) 6/24/2019 low pressure drum-separator (LPDS) 6/24/2019 low-pressure heater (LPH) 6/24/2019 medium pressure cylinder (MPC) 6/24/2019 medium pressure drum-separator (MPDS) 6/24/2019 Siemens SGT-9000HL 6/24/2019 steam module 6/24/2019 turbine plant (TP) 6/24/2019 annealing of the reactor vessel 6/24/2019 fluence 6/24/2019 radiation embrittlement 6/24/2019 re-extension of service life 6/24/2019 safety systems 6/24/2019 V-179 6/24/2019 BN 6/24/2019 critical test benches 6/24/2019 heterogeneous effect 6/24/2019 neutron physical calculation 6/24/2019 simulation of nuclear reactors 6/24/2019 sodium void reactivity effect 6/24/2019 equipment life 6/24/2019 thermal fatigue 6/24/2019 coolant flow rate 6/24/2019 departure from nucleate boiling (DNB) 6/24/2019 experimental fuel assembly (EFA) 6/24/2019 MIR reactor 6/24/2019 natural uranium resources 6/24/2019 nuclear energy development scenarios 6/24/2019 power 6/24/2019 RIA (reactivity-initiated accident) 6/24/2019 SNF reprocessing 6/24/2019 SNF reprocessing value 6/24/2019 spent nuclear fuel (SNF) 6/24/2019 thermoelectric converter (TEC) 6/24/2019 axial pump 6/24/2019 pump delivery rate 6/24/2019 pump head 6/24/2019 pump impeller 6/24/2019 analytical solution 6/24/2019 fuel temperature field 6/24/2019 influence of tuning coefficients 6/24/2019 mathematical model to determine fuel temperature fields 6/24/2019 safety of fuel rod heating 6/24/2019 verification of numerical calculations 6/24/2019 carbon dioxide 6/24/2019 effective range approximation 6/24/2019 resonance and shadow poles 6/24/2019 resonance coupled channel method 6/24/2019 S-matrix poles 6/24/2019 digital economy in power engineering 6/24/2019 education export 6/24/2019 educational technologies 6/24/2019 staff training 6/24/2019 educational portal 6/24/2019 graph database 6/24/2019 knowledge graph 6/24/2019 ontology 6/24/2019 export strategy 6/24/2019 nuclear education 6/24/2019 personal training 6/24/2019 data integration 3/25/2019 JSON-format 3/25/2019 reactor materials 3/25/2019 thermophysical properties 3/25/2019 contour code 3/25/2019 off-nominal situation 3/25/2019 shutdown of the MCP 3/25/2019 accumulation 3/25/2019 emergency mode 3/25/2019 solubility 3/25/2019 steam 3/25/2019 crisis of heat exchange 3/25/2019 energy release 3/25/2019 neural nets 3/25/2019 thermalphysic model 3/25/2019 complexation 3/25/2019 membrane permeability 3/25/2019 nanofiltration 3/25/2019 osmotic pressure 3/25/2019 radwaste 3/25/2019 reverse osmosis 3/25/2019 RO 3/25/2019 non-proliferation resistant 3/25/2019 reprocessed uranium 3/25/2019 resources saving 3/25/2019 coated particles 3/25/2019 fast sodium reactors 3/25/2019 fuel assemblies with coated particles 3/25/2019 inherent safety 3/25/2019 microfuel 3/25/2019 microspherical fuel 3/25/2019 mixed carbide fuel 3/25/2019 tolerant fuel 3/25/2019 beyond design accident 3/25/2019 passive residual heat removal system 3/25/2019 reactor safety 3/25/2019 subcriticality 3/25/2019 dimensional effect 3/25/2019 fiber glass 3/25/2019 polymer composite materials 3/25/2019 scaling factor 3/25/2019 strength 3/25/2019 Weibull statistical model 3/25/2019 dismantling 3/25/2019 extraction column 3/25/2019 foam decontamination 3/25/2019 radiation-contaminated equipment 3/25/2019 tanks 3/25/2019 uranium 3/25/2019 integrated engineering radiological survey 3/25/2019 route optimization 3/25/2019 unscheduled measurements 3/25/2019 virtual training 3/25/2019 concept 3/25/2019 monitoring regulations 3/25/2019 radiation hazardous facilities 3/25/2019 centralized global parallel search circuit 3/25/2019 electro-optical neural commuting system 3/25/2019 high-temperature gas-cooled reactors 3/25/2019 hydrogen production forecasting 3/25/2019 spiking neural networks 3/25/2019 deposited dose 3/25/2019 Monte Carlo simulation 3/25/2019 nanoparticles of gold and gadolinium 3/25/2019 photon beam therapy 3/25/2019 advantages of the VVER-SKD concept 11/15/2018 GIF-IV program 11/15/2018 number of publications 11/15/2018 problems of developing the VVER-SKD 11/15/2018 proposals for cooperation 11/15/2018 prospects for nuclear power development 11/15/2018 supercritical water reactor (SCWR) 11/15/2018 Doppler effect 11/15/2018 gap conductance coefficient 11/15/2018 core shaping 11/15/2018 mass flow distribution 11/15/2018 maximum channel wall temperature 11/15/2018 electrochemical behavior of thorium 11/15/2018 fuel reprocessing 11/15/2018 options 11/15/2018 oxide fuel 11/15/2018 pyroelectrochemical processes 11/15/2018 thorium fuel cycle 11/15/2018 barrier 11/15/2018 furnace channel 11/15/2018 gas sampling 11/15/2018 gas-dynamic investigations 11/15/2018 measuring gas concentration 11/15/2018 modelling gas concentration distribution 11/15/2018 sintering furnace 11/15/2018 zone of furnace 11/15/2018 assessment of brittle fracture resistance 11/15/2018 conservative vessel life estimations 11/15/2018 critical brittle point TK 11/15/2018 ductile-to-brittle-transition-temperature TP 11/15/2018 padding and welded joints 11/15/2018 composite decontaminating material 11/15/2018 decontamination 11/15/2018 film-forming compositions 11/15/2018 fixed radioactive contamination 11/15/2018 economic efficiency indicators 11/15/2018 economic risk 11/15/2018 modular NPP 11/15/2018 small and medium sized reactors 11/15/2018 absolute efficiency curve 11/15/2018 gamma spectrometry 11/15/2018 ISOCS system 11/15/2018 MCNP code 11/15/2018 measurement procedure 11/15/2018 measurement procedure range 11/15/2018 nondestructive analysis of nuclear materials 11/15/2018 solid radioactive waste 11/15/2018 uranium mass 11/15/2018 calculation code 11/15/2018 nuclear neutron reactions 11/15/2018 nuclear transmutation chains 11/15/2018 nuclide 11/15/2018 nuclide kinetics problem 11/15/2018 radioactive decay 11/15/2018 delivery nanoconstructs 11/15/2018 magnetite 11/15/2018 radiopharmaceuticals 11/15/2018 radium-223, magnetic nanoparticles 11/15/2018 short-lived alpha radionuclides 11/15/2018 targeted alpha-therapy 11/15/2018 absorbed dose 11/15/2018 compartmental model 11/15/2018 databases 11/15/2018 domain modeling 11/15/2018 domain voxelization 11/15/2018 farm animals 11/15/2018 on-line calculations 11/15/2018 radiation accident 11/15/2018 radiation transport modeling 11/15/2018 radioactive iodine 11/15/2018 thyroid gland 11/15/2018 nuclear icebreaking fleet 9/20/2018 accelerogram 9/20/2018 dynamic analysis method 9/20/2018 finite element model 9/20/2018 linear spectral method 9/20/2018 reduced stresses 9/20/2018 seismic stability 9/20/2018 IAEA 9/20/2018 peak ground acceleration 9/20/2018 seismic acceleration and damage 9/20/2018 seismic hazard parameters 9/20/2018 descriptor 9/20/2018 neutron induced activity 9/20/2018 nuclear facilities 9/20/2018 radiation shielding concrete 9/20/2018 delays in NPP construction 9/20/2018 human factor 9/20/2018 project management 9/20/2018 ENDF libraries 9/20/2018 infologic modeling 9/20/2018 relational format 9/20/2018 alpha-particles transport 9/20/2018 disperse nuclear fuel 9/20/2018 isotopic composition 9/20/2018 radiation sources spectrum 9/20/2018 thorium reactor 9/20/2018 heat exchanger 9/20/2018 horizontal type steam generator 9/20/2018 light water reactor type 9/20/2018 pre-boiling section 9/20/2018 separators of chevron and swirl-vane type 9/20/2018 steam-water mixture 9/20/2018 temperature difference 9/20/2018 the four-loop layout 9/20/2018 variable thermocyclic stress 9/20/2018 vertical type steam generator 9/20/2018 forecasting 9/20/2018 MESSAGE 9/20/2018 MNUP 9/20/2018 UOX 9/20/2018 18-month fuel cycle 9/20/2018 effective days 9/20/2018 fuel enrichment 9/20/2018 fuel reloading scheme 9/20/2018 natural days 9/20/2018 operating costs 9/20/2018 PROSTOR 9/20/2018 gaseous fission products 9/20/2018 UO2 dissolution 9/20/2018 departure from nuclear boiling 9/20/2018 heat sink failure 9/20/2018 high-speed dump valves with discharge to atmosphere (HSDV-A) 9/20/2018 pipeline break 9/20/2018 safety factor 9/20/2018 stop valve 9/20/2018 coolant flow measurement system 9/20/2018 distribution function 9/20/2018 exponential estimate 9/20/2018 mathematical time expectation 9/20/2018 parametric reliability 9/20/2018 random process 9/20/2018 random variables 9/20/2018 time to failure 9/20/2018 accuracy evaluation 9/20/2018 BFS critical facility 9/20/2018 constant error 9/20/2018 effective multiplication factor 9/20/2018 maximum likelihood method 9/20/2018 hydrated sodium metasilicate 9/20/2018 oxide and calcium hydroxide 9/20/2018 the oxide layer 9/20/2018 acoustic flows 6/22/2018 cavitation 6/22/2018 heat transfer equipment 6/22/2018 quality cleaning 6/22/2018 technology 6/22/2018 ultrasound 6/22/2018 microwave reflex-radar level gauge 6/22/2018 power-generating equipment 6/22/2018 water coolant at high temperatures and pressures (310 °C, 10 MPa) 6/22/2018 calculation model 6/22/2018 deregulated market 6/22/2018 electricity cost 6/22/2018 financially integrated system 6/22/2018 financing instruments 6/22/2018 nuclear energy business 6/22/2018 chemical explosive 6/22/2018 cryogenic temperatures 6/22/2018 nuclear explosive device 6/22/2018 plutonium 238 6/22/2018 proliferation protection 6/22/2018 further refinement 6/22/2018 introduction in the practice of calculations 6/22/2018 new ROCOCO combined system of neutron constant preparation 6/22/2018 potential of development 6/22/2018 results of comparative calculations 6/22/2018 artificial neural networks 6/22/2018 criticality margin 6/22/2018 generalized approximation theorem 6/22/2018 software package 6/22/2018 WWR c reactor 6/22/2018 cavities calculations 6/22/2018 fast breeder reactor 6/22/2018 mixed nitride uranium-plutonium SNF (MNUP SNF) 6/22/2018 on-line monitoring of nuclear materials 6/22/2018 pyrochemical process 6/22/2018 pyroelectrochemical refining 6/22/2018 consequences of radiological accident 6/22/2018 decision-making criteria 6/22/2018 protective measures 6/22/2018 radioactive release 6/22/2018 severe accident 6/22/2018 fission product 6/22/2018 iodine radionuclide 6/22/2018 radioactive noble gases 6/22/2018 technique 6/22/2018 WWER 6/22/2018 hydrogen distribution 6/22/2018 lumped parameter model 6/22/2018 SIMCO code 6/22/2018 biological protection 6/22/2018 current-voltage characteristic 6/22/2018 flexural strength 6/22/2018 heat resistance 6/22/2018 information-measuring complex 6/22/2018 neutron shielding characteristics 6/22/2018 polyalkaneimide 6/22/2018 pulsed mode 6/22/2018 relaxation length 6/22/2018 shearing cross section 6/22/2018 thermionic converter 6/22/2018 thermocouples 6/22/2018 titanium hydride 6/22/2018 code generation 6/22/2018 instrumentation tools 6/22/2018 microcontroller 6/22/2018 reverse engineering 6/22/2018 multi-criteria analysis 6/22/2018 nuclear data 6/22/2018 spallation nuclear reactions 6/22/2018 main components 3/23/2018 SG intercircuit seal breakdown 3/23/2018 small and medium sized reactor plant 3/23/2018 technical solutions 3/23/2018 acoustoelasticity 3/23/2018 early diagnosis 3/23/2018 elastic moduli 3/23/2018 equations 3/23/2018 tension 3/23/2018 americium-241 3/23/2018 metallic uranium-plutonium fuel 3/23/2018 natural lead coolant 3/23/2018 combination of detailed and group descriptions of cross-section energy dependences 3/23/2018 radiation field calculation using the Monte Carlo method 3/23/2018 absorber element 3/23/2018 aluminum alloys SAV-1 and ASD-4 3/23/2018 control and protection system (CPS) 3/23/2018 crystalline sodium metasilicate hydrates 3/23/2018 lime 3/23/2018 power coefficient of reactivity 3/23/2018 RBMK-1000 reactor 3/23/2018 rod control cluster assembly (RCCA) 3/23/2018 sodium and potassium water glass 3/23/2018 temperature coefficients of reactivity 3/23/2018 Russian Arctic regions 3/23/2018 small nuclear power plants 3/23/2018 irradiated reactor-grade graphite 3/23/2018 uranium graphite reactor 3/23/2018 fission product escape 3/23/2018 fuel damage dynamics 3/23/2018 release 3/23/2018 severe beyond design basis accident 3/23/2018 additional diagnostic signs 3/23/2018 dispersion of the acoustic signal 3/23/2018 leakage test equipment 3/23/2018 modeling of leaks of the coolant 3/23/2018 pattern recognition 3/23/2018 the method of main components 3/23/2018 coolant leak 3/23/2018 design analysis 3/23/2018 hydroaccumulator 3/23/2018 safe state 3/23/2018 spillage system 3/23/2018 the core 3/23/2018 brittle fracture resistance 3/23/2018 conservative estimations 3/23/2018 critical brittleness temperature 3/23/2018 ductile-to-brittle transition temperature 3/23/2018 standard deviation 3/23/2018 automated control systems 3/23/2018 computer modeling 3/23/2018 diversity 3/23/2018 fuel burnup fraction 11/28/2017 hydrocarbons 11/28/2017 non-renewable traditional energy resources 11/28/2017 nuclear reactor breeders 11/28/2017 production dynamics 11/28/2017 production peak 11/28/2017 production rate 11/28/2017 ampoule channel with natural circulation 11/28/2017 power of energy release 11/28/2017 research reactor SM 11/28/2017 research results 11/28/2017 temperature regimes of irradiation 11/28/2017 fission power peaking factor 11/28/2017 genetic algorithm 11/28/2017 step of lattice 11/28/2017 thermionic conversion reactor 11/28/2017 thermionic fuel elements 11/28/2017 diffusion equation 11/28/2017 multigroup approximation 11/28/2017 neutron transport 11/28/2017 subcritical systems 11/28/2017 electrically heated fuel rod dummy 11/28/2017 experimental fuel rod 11/28/2017 heating rate 11/28/2017 hot junction 11/28/2017 lab-scale facility 11/28/2017 loss-of-oolant accident (LOCA) 11/28/2017 reactor MIR 11/28/2017 spacer grid 11/28/2017 thermocouple 11/28/2017 droplet 11/28/2017 thermal physical properties of boric acid solution 11/28/2017 bends 11/28/2017 FAC rate estimation 11/28/2017 flow-accelerated corrosion 11/28/2017 minimal admissible wall thickness 11/28/2017 residual life time 11/28/2017 wall thickness control data 11/28/2017 welding 11/28/2017 data transmission 11/28/2017 maximum estimated earthquake 11/28/2017 Seismic Protection System 11/28/2017 seismic station 11/28/2017 shutdown 11/28/2017 conversion 11/28/2017 coolant technology 11/28/2017 dislocations 11/28/2017 ENDF library 11/28/2017 irradiation hardening 11/28/2017 metals 11/28/2017 oxidation kinetics 11/28/2017 precipitates 11/28/2017 steel oxidation 11/28/2017 voids 11/28/2017 yield strength 11/28/2017 binding energy 11/28/2017 radiocarbon 11/28/2017 radionuclide 11/28/2017 strength of fixation 11/28/2017 treatment 11/28/2017 accumulator tank 10/02/2017 APCS 10/02/2017 equipment 10/02/2017 power unit 10/02/2017 rector 10/02/2017 safety system 10/02/2017 flow rate 10/02/2017 level 10/02/2017 pump 10/02/2017 turbine generator 10/02/2017 common cause failure, software 10/02/2017 control safety systems 10/02/2017 diverse protection system 10/02/2017 protection algorithms 10/02/2017 measured parameters 10/02/2017 model validation 10/02/2017 operation data 10/02/2017 technical state analysis 10/02/2017 unit status change prediction 10/02/2017 combination of functions 10/02/2017 ejector 10/02/2017 emergency cooldown 10/02/2017 fuel cooling 10/02/2017 redundancy 10/02/2017 reliability 10/02/2017 safety case 10/02/2017 Automated Process Control System 10/02/2017 broadcast storm 10/02/2017 cybersecurity 10/02/2017 a function of the coherence 10/02/2017 commissioning 10/02/2017 commissioning measurement 10/02/2017 natural frequency 10/02/2017 phase characteristics 10/02/2017 portable analyzer 10/02/2017 the oscillations of the pendulum type 10/02/2017 vibration control 10/02/2017 diagnostic system 10/02/2017 in-core monitoring system 10/02/2017 invalid readings 10/02/2017 measuring monitoring channels 10/02/2017 decentralization of control functions 10/02/2017 functional safety 10/02/2017 information controlling system 10/02/2017 nuclear plant 10/02/2017 refueling machine 10/02/2017 single failure 10/02/2017 detection of neutron flux density 10/02/2017 measuring channel 10/02/2017 NFME 10/02/2017 power readings correction 10/02/2017 reactor power 10/02/2017 reactor unit 10/02/2017 dummy fuel assembly 10/02/2017 first criticality 10/02/2017 excitation regulator 10/02/2017 excitation system 10/02/2017 Novovoronezh NPP 10/02/2017 relay protection 10/02/2017 sustainability 10/02/2017 eddy-current testing 10/02/2017 preoperational inspection 10/02/2017 ultrasonic testing 10/02/2017 ultrasonic testing technology 10/02/2017 blowdown 10/02/2017 upgrading 10/02/2017 V-392M reactor plant 10/02/2017 water chemistry 10/02/2017 AES-2006 design 10/02/2017 air valve 10/02/2017 passive heat removal system 10/02/2017 pre-commissioning 10/02/2017 regulator 10/02/2017 V-392M 10/02/2017 chemical water treatment 10/02/2017 cleansing 10/02/2017 design chemistry 10/02/2017 passivation 10/02/2017 preliminary treatment 10/02/2017 radioactive water treatment 10/02/2017 reagents 10/02/2017 sedimentation 10/02/2017 Novovoronezh NPP II 10/02/2017 gadolinium 10/02/2017 high fuel burn-up 10/02/2017 protactinium-231 10/02/2017 stabilized multiplying properties 10/02/2017 very long fuel campaign 10/02/2017 corrosion resistance 6/21/2017 detonation waves 6/21/2017 oxygen ions 6/21/2017 reactor cooling system 6/21/2017 stainless steel 6/21/2017 water electrolysis 6/21/2017 water molecule 6/21/2017 abstract homogeneous flow 6/21/2017 aging system 6/21/2017 counting process 6/21/2017 failure flow 6/21/2017 intensity function 6/21/2017 juvenescent system 6/21/2017 non-homogeneous event flow 6/21/2017 normalizing flow function model (NFF) 6/21/2017 renewal equation 6/21/2017 index of indeterminacy 6/21/2017 larger data 6/21/2017 management of risk 6/21/2017 residual risk 6/21/2017 risk degree 6/21/2017 sensitivity of risk 6/21/2017 3He-counter 6/21/2017 active control 6/21/2017 fissile materials 6/21/2017 gamma background 6/21/2017 SFA 6/21/2017 control rods effectiveness 6/21/2017 core simulation 6/21/2017 critical assembly 6/21/2017 fast neutrons reactors 6/21/2017 nuclear material accounting and control 6/21/2017 physical protection 6/21/2017 power distribution 6/21/2017 reactivity effects 6/21/2017 sodium void effect reactivity 6/21/2017 austenitic stainless steel 6/21/2017 ion-plasma treatment 6/21/2017 slip deformation 6/21/2017 stacking faults 6/21/2017 twinning deformation 6/21/2017 X-ray diffraction-pattern 6/21/2017 burnup value 6/21/2017 optimization of fuel loading and reloading 6/21/2017 finite element analysis 6/21/2017 single-cell thermionic fuel element 6/21/2017 thermionic NPP 6/21/2017 three-dimensional numerical modeling 6/21/2017 dynamics of nuclear reactor 6/21/2017 integral equations 6/21/2017 point kinetics 6/21/2017 quadrature formulas 6/21/2017 attractiveness of reactor fuel for unauthorized applications 6/21/2017 beryllium 6/21/2017 BR-1200 fast reactor 6/21/2017 critical system with neutron reflectors 6/21/2017 mixed nitride uranium-plutonium fuel 6/21/2017 uranium nitride 6/21/2017 transmutation coefficient 6/21/2017 aluminum alloy 6/21/2017 heat-affected zone 6/21/2017 influence of ultrasound 6/21/2017 residual stress 6/21/2017 inelastic neutron scattering 6/21/2017 neutron spectra 6/21/2017 time-of-flight method 6/21/2017 verification of evaluated neutron data 6/21/2017 radioactive pollution 6/21/2017 radiochemical enterprise 6/21/2017 surface layer of the atmosphere 6/21/2017 volumetric activity 6/21/2017 discount rate 6/21/2017 NPP competitiveness 6/21/2017 nuclear power reactor 6/21/2017 on-line monitoring 3/22/2017 surge line 3/22/2017 thermal stratification 3/22/2017 thermomechanical load 3/22/2017 condensation mode 3/22/2017 contact condensation 3/22/2017 non-condensable gases 3/22/2017 steam-gas mixture 3/22/2017 passive safety systems 3/22/2017 pattern recognition theory 3/22/2017 principal component method 3/22/2017 pump diagnostics 3/22/2017 PWR 3/22/2017 set of informative criteria 3/22/2017 steam generators 3/22/2017 failure time 3/22/2017 mean time 3/22/2017 random values 3/22/2017 security system 3/22/2017 stochastic process 3/22/2017 16Cr-15Ni-2Mo-Mn-Ti-V-B steel 3/22/2017 maximum swelling temperature 3/22/2017 heat 3/22/2017 thermodynamic modeling 3/22/2017 analytical ratios 3/22/2017 critical condition 3/22/2017 equilibrium mode 3/22/2017 fast butch pulsed reactor 3/22/2017 laser system 3/22/2017 STIK program 3/22/2017 subcritical block 3/22/2017 cellular neural networks 3/22/2017 forecasting temperature fields 3/22/2017 heavy water reactor 3/22/2017 optical neurons 3/22/2017 oscillating fractal network 3/22/2017 stochastic algorithms for neural networks training 3/22/2017 the heating medium neutron moderator 3/22/2017 degradation degree 3/22/2017 hexachlorane dust 3/22/2017 isomers: γ-HCH 3/22/2017 lindane 3/22/2017 organochlorinated pesticide 3/22/2017 pesticidal chemical 3/22/2017 radiation destruction 3/22/2017 radiation stability 3/22/2017 stereo isomerization 3/22/2017 α-HCH 3/22/2017 β-HCH 3/22/2017 γ -irradiation dose 3/22/2017 adsorbent 3/22/2017 heavy metals 3/22/2017 sorption capacity 3/22/2017 water treatment 3/22/2017 compatibility with material control and accounting system 3/22/2017 hardware and software 3/22/2017 input and output data 3/22/2017 nuclear materials control and accounting 3/22/2017 system for management of specialized data base of plutonium 3/22/2017 pump flow 3/22/2017 RCP (reactor coolant pump) 3/22/2017 reactor plant on fast neutrons 3/22/2017 active and passive imagemaking 3/22/2017 implicit memory 3/22/2017 nuclear power industry 3/22/2017 psychological deprivation 3/22/2017 psychological frustration 3/22/2017 stereotype 3/22/2017 comparative evaluation 3/22/2017 economic risks 3/22/2017 reactor technologies 3/22/2017 residual stresses 12/25/2016 Karhunen-Loeve transform 12/25/2016 main circulation pumps (MCP) operation and diagnostics 12/25/2016 MCP abnormal condition 12/25/2016 heterogeneous composition 12/25/2016 hydrozirconium reaction 12/25/2016 sodium liquid glass 12/25/2016 zirconium 12/25/2016 zirconium oxide 12/25/2016 damage 12/25/2016 manifold 12/25/2016 refusal 12/25/2016 zone of a welded joint 12/25/2016 engineering barriers 12/25/2016 host medium 12/25/2016 justification of safety 12/25/2016 natural frequencies 12/25/2016 nuclear legacy 12/25/2016 oscillation of pendulum type 12/25/2016 phase 12/25/2016 radiation transport 12/25/2016 radionuclide migration 12/25/2016 simulation analysis 12/25/2016 the coherence function 12/25/2016 Fukushima-Daiichi accident 12/25/2016 public protection strategy 12/25/2016 radiation emergency 12/25/2016 stress test 12/25/2016 comparative analysis 12/25/2016 direct conversion of energy 12/25/2016 domestic and foreign installations 12/25/2016 nuclear installations 12/25/2016 nuclear propulsions 12/25/2016 space nuclear power 12/25/2016 aerogel 12/25/2016 anisotropic nanostructure 12/25/2016 bismuth 12/25/2016 ceramic materials 12/25/2016 gallium 12/25/2016 liquid metal fusions 12/25/2016 impurity 12/25/2016 melt 12/25/2016 oxide 12/25/2016 partial pressure 12/25/2016 thermodynamic analysis 12/25/2016 a three-loop diagram 12/25/2016 corrosion products 12/25/2016 high-temperature 12/25/2016 integral arrangement 12/25/2016 security 12/25/2016 system cleaning 12/25/2016 ADS 12/25/2016 MCNPX 12/25/2016 neutron yield 12/25/2016 spallation neutron sours target 12/25/2016 complex model 12/25/2016 control systems algorithms 12/25/2016 design 12/25/2016 MBIR reactor facility 12/25/2016 neutron physics processes 12/25/2016 PRISET calculation code 12/25/2016 safety analysis 12/25/2016 SimInTech process systems dynamic modeling environment 12/25/2016 thermal hydraulic processes 12/25/2016 backup electricity supply for covering auxiliary needs of the NPP 10/02/2016 combined cycle gas turbine unit 10/02/2016 combustion chamber 10/02/2016 emergency electricity supply 10/02/2016 hydrogen cycle 10/02/2016 maneuverability 10/02/2016 nuclear emergency with complete loss of electric power supply 10/02/2016 automated ultrasound system 10/02/2016 the ultrasonic method of stress relief 10/02/2016 welded joints 10/02/2016 failure flow, intensity function 10/02/2016 nonhomogeneous event flow 10/02/2016 control and management of nuclear facilities 10/02/2016 dispersion equation 10/02/2016 metrology 10/02/2016 reactivity meter 10/02/2016 FA bowing 10/02/2016 FA skeleton 10/02/2016 flexural rigidity 10/02/2016 crisis of boiling 10/02/2016 disturbance of heat with drawal 10/02/2016 regime 10/02/2016 stock coefficient 10/02/2016 analytical simulator 10/02/2016 nuclear power system 10/02/2016 competences 10/02/2016 knowledge management 10/02/2016 metascience 10/02/2016 methods of nuclear knowledge management 10/02/2016 series of interpretative theories 10/02/2016 drop to pin 10/02/2016 Johnson-Cook plasticity model 10/02/2016 Johnson-Cook plasticity model parameters calculation 10/02/2016 SNF container 10/02/2016 laser system pumped by nuclear reactor 10/02/2016 neutron kinetics 10/02/2016 pulse energy and maximum power 10/02/2016 hydrogen production 10/02/2016 neutronics 10/02/2016 pooltype configuration 10/02/2016 safety issues, steels 10/02/2016 thermal physics 10/02/2016 heat transfer in nuclear reactor 10/02/2016 pooltype research reactor 10/02/2016 VVR-c fuel assemblies 10/02/2016 VVR-M2 10/02/2016 VVR-M3 10/02/2016 VVR-M5 10/02/2016 decay heat removal 10/02/2016 emergency heat removal system 10/02/2016 PHENIX 10/02/2016 competitive 10/02/2016 degenerate optimization problem 10/02/2016 electric power system 10/02/2016 noncompetitive 10/02/2016 nonoptimality 10/02/2016 optimality 10/02/2016 power plant 10/02/2016 rate of discount 10/02/2016 beam’s super characteristics 10/02/2016 combined target 10/02/2016 heat removal 10/02/2016 protection of the patient 10/02/2016 up-to-date medical technologies 10/02/2016 control of basic doses 10/02/2016 planar stratigraphy 10/02/2016 radionuclide therapy 10/02/2016 main control room operator 3/28/2016 operator support system 3/28/2016 support function 3/28/2016 task of support 3/28/2016 heavyion implantation 3/28/2016 nanostructures 3/28/2016 radiation-induced processes 3/28/2016 customproject 3/28/2016 stress condition 3/28/2016 attractiveness of nuclear materials 3/28/2016 critical assemblies 3/28/2016 fast sodium reactor of large capacity 3/28/2016 mixed oxide uranium-plutonium fuel 3/28/2016 neutron reflector 3/28/2016 non-proliferation of nuclear weapons 3/28/2016 uranium oxide 3/28/2016 aluminium 3/28/2016 aluminium oxide 3/28/2016 event tree 3/28/2016 fault tree 3/28/2016 irradiation dose 3/28/2016 nuclear installation 3/28/2016 probabilistic safety analysis 3/28/2016 software 3/28/2016 the kinetics of generation 3/28/2016 transformation of the oxide coating 3/28/2016 acoustic method 3/28/2016 analysis of the most “hot spots” 3/28/2016 automated control system 3/28/2016 corrosion products deposit 3/28/2016 diagnostics system 3/28/2016 emergency 3/28/2016 identifying violations 3/28/2016 probabilistic model 3/28/2016 procedure of flow-accelerated corrosion rate estimation 3/28/2016 residual service life 3/28/2016 stochastic model 3/28/2016 the state of the stator winding 3/28/2016 turbo generator 3/28/2016 BFS critical assemblies 3/28/2016 heavy-ion implantation 3/28/2016 integral critical experiments 3/28/2016 MCNP 3/28/2016 reaction rate ratios 3/28/2016 variance reduction methods 3/28/2016 error 3/28/2016 normal operation 3/28/2016 program 3/28/2016 static parameters 3/28/2016 Bateman equations 3/28/2016 decay chain 3/28/2016 graph theory 3/28/2016 information systems 3/28/2016 interactive interface 3/28/2016 KLT-40S 3/28/2016 microscopic model of hadron-nucleus interaction 3/28/2016 reproduction rate 3/28/2016 the effective multiplication factor 3/28/2016 the uranium fuel cycle 3/28/2016 BFS facility 3/28/2016 critical experiments 3/28/2016 evaluated neutron data 3/28/2016 neutron transmission 3/28/2016 ROSFOND library 3/28/2016 Energy planning 3/28/2016 maximum neutron flux 3/28/2016 metalic fuel 3/28/2016 multi-criteria optimization 3/28/2016 multipurpose research sodium cooled fast reactor (MBIR) 3/28/2016 Ea histogram 3/28/2016 superlong fuel residence 3/28/2016 the event flow 3/28/2016 the Monte Carlo method 3/28/2016 the test statistic 3/28/2016 thoriumloaded lowpower reactor installation 3/28/2016 BNAB 3/28/2016 calculations of fast reactors 3/28/2016 computer code 3/28/2016 equivalence function 3/28/2016 multigroup nuclear constants 3/28/2016 neutron data files 3/28/2016 radiation shielding 3/28/2016 scenario 3/28/2016 storage 3/28/2016 storage topology 3/28/2016 equivalent dose 3/28/2016 isotope composition 3/28/2016 plutonium multirecycling 3/28/2016 uranium multirecycling 3/28/2016 water moderated water cooled power reactor 3/28/2016 calculation 3/28/2016 HLMC RP 3/28/2016 hybrid «FUSION-FISSION» reactor with Th-blanket 3/28/2016 light uranium fraction 3/28/2016 melting unit 3/28/2016 multi-isotope uranium fuel 3/28/2016 steam leak between circuits 3/28/2016 steel vessel 3/28/2016 surface 3/28/2016 the protection of fissile materials against uncontrolled proliferation 3/28/2016 the stabilization of multiplication properties 3/28/2016 fluids 3/28/2016 heat rate 3/28/2016 hydrogen concentration 3/28/2016 irradiation rig 3/28/2016 samples 3/28/2016 seismological monitoring 3/28/2016 suffosionkarst processes 3/28/2016 weak seismicity 3/28/2016 an annular gap 3/28/2016 the annular channel 3/28/2016 corrosion control 3/28/2016 mass exchanger 3/28/2016 oxygen content 3/28/2016 oxygen sensor 3/28/2016 competitive strength 3/28/2016 nuclear fuel and energy complex 3/28/2016 power engineering 3/28/2016 system 3/28/2016 nuclear emergency 12/25/2015 protection strategy 12/25/2015 safety requirements 12/25/2015 coupled parameters of steam 12/25/2015 fire overheating 12/25/2015 heat pump 12/25/2015 waste heat 12/25/2015 a piezoelectric transducer 12/25/2015 acoustic waveguide 12/25/2015 power equipment 12/25/2015 reflex-radar principles 12/25/2015 ultrasonic waveguide level 12/25/2015 water coolant of high parameters (350°C, 18 MPa) 12/25/2015 frequency rate of weakening 12/25/2015 homogenous radiation protective material 12/25/2015 research nuclear reactor 12/25/2015 reactor irradiation 12/25/2015 structural studies 12/25/2015 temperature monitor 12/25/2015 ion irradiation 12/25/2015 metallic glass 12/25/2015 nanostructure 12/25/2015 plastic deformation 12/25/2015 education algorithm 12/25/2015 NPP piping 12/25/2015 temperature modes of irradiation 12/25/2015 CAD 12/25/2015 data exchange 12/25/2015 scalable vector graphics 12/25/2015 SVG 12/25/2015 helical wires 12/25/2015 model fuel assembly 12/25/2015 Nusselt number 12/25/2015 smooth fuel pins 12/25/2015 temperature non-uniformities 12/25/2015 cascade function defects 12/25/2015 reactor graphite 12/25/2015 stored energy 12/25/2015 Wigner energy 12/25/2015 determine the mass of plutonium and enrichment 12/25/2015 method of neutron coincidence 12/25/2015 neutron detection efficiency 12/25/2015 cavitation pump head 12/25/2015 design centrifugal and axial vane-pump system 12/25/2015 MCP 12/25/2015 reactor installation on fast neutrons 12/25/2015 an optimality 12/25/2015 non-optimality 12/25/2015 filter 10/23/2015 heat and mass transfer 10/23/2015 heater 10/23/2015 hot trap 10/23/2015 purification system 10/23/2015 ecological constraints 10/23/2015 emission cost 10/23/2015 fiber-optic sensors based on lithium 10/23/2015 heterogeneous scintillation detector 10/23/2015 multilayered neutron detector 10/23/2015 γ-background discrimination 10/23/2015 electrical resistivity graph 10/23/2015 gamma nuclide graph 10/23/2015 hexagonal geometry 10/23/2015 neutronics calculations 10/23/2015 nodal method 10/23/2015 SN-approximation 10/23/2015 heat and mass transferal 10/23/2015 mixing grid 10/23/2015 the coolant flow hydrodynamic 10/23/2015 Euler number 10/23/2015 geometrical distortion of model 10/23/2015 imitator channel 10/23/2015 modeling scale 10/23/2015 operation technological channel 10/23/2015 pressure drop 10/23/2015 reacto fuel assembly 10/23/2015 Reynolds number 10/23/2015 thermohydraulic reactor core model 10/23/2015 boiling 10/23/2015 experimental investigation 10/23/2015 fuel subassembly mockup 10/23/2015 intensification of coolant’s mixing 10/23/2015 nuclear reactor core 10/23/2015 secondary flows 10/23/2015 two-phase flow 10/23/2015 coolant hydrodynamics 10/23/2015 spacer and mixing grids 10/23/2015 criteria of technical level 10/23/2015 parametric analysis 10/23/2015 sensitivity function 10/23/2015 space nuclear power plants 10/23/2015 calculation 3D-model 10/23/2015 fuel block a unified design 10/23/2015 gas-cooled thorium reactor 10/23/2015 education and training 10/23/2015 fuel hard neutron spectrum 10/23/2015 lead fast reactor 10/23/2015 small stock of reactivity 10/23/2015 small thermal power 10/23/2015 crater 10/23/2015 lunar surface 10/23/2015 rate of discounting 10/23/2015 4th generation nuclear reactors 9/01/2015 current status 9/01/2015 electricity generation 9/01/2015 modern nuclear power plants 9/01/2015 thermal power plants 9/01/2015 an average approximation error 9/01/2015 background readings 9/01/2015 bar chart 9/01/2015 BN-600 9/01/2015 capacity 9/01/2015 delayedneutrons 9/01/2015 detection unit 9/01/2015 regression model 9/01/2015 sectoral monitoring system leak fuel cladding 9/01/2015 instability of metrological characteristics 9/01/2015 the theory of Taguchi 9/01/2015 stand-alone hydrogen generator 9/01/2015 beyond-basic accident 9/01/2015 code KUPOL-BN 9/01/2015 code NOSTRADAMUS 9/01/2015 safety analysis of FBR 9/01/2015 system code SOCRAT-BN 9/01/2015 fission 9/01/2015 kinetic processes 9/01/2015 laser radiation 9/01/2015 moving plasma 9/01/2015 nanoparticles 9/01/2015 transformation 9/01/2015 uranium fragments 9/01/2015 sodium fast reactor BN-600 9/01/2015 steam methane reforming 9/01/2015 computer and full'scale simulators 9/01/2015 numerical experiments 9/01/2015 training of personnel 9/01/2015 xenon stability in a nuclear reactor 9/01/2015 separation of steam-water mixture 9/01/2015 steam volume fraction 9/01/2015 steam-water flow pattern 9/01/2015 axial-burnup 9/01/2015 distribution 9/01/2015 transportation 9/01/2015 fuel burn-up 9/01/2015 mixed nitride fuel 9/01/2015 mixed oxide fuel 9/01/2015 transitional mode operation 9/01/2015 multiplication factor 9/01/2015 plutonium isotope composition 9/01/2015 sensitivity coefficients 9/01/2015 fast sodium reactor 9/01/2015 fuel volume fraction 9/01/2015 metallic fuel 9/01/2015 nitride uranium-plutonium fuel 9/01/2015 reactivity margin for burn-up 9/01/2015 ecological zone 9/01/2015 land cover 9/01/2015 mollusc Bradybaena Fruticicola fruticum 9/01/2015 Sr-90 9/01/2015 the dose rate 9/01/2015 burning minor actinides 4/04/2015 closure of the fuel cycle 4/04/2015 international forum «Generation IV» 4/04/2015 the spent nuclear fuel 4/04/2015 nuclear emergency with blackou 4/04/2015 reserve auxiliary of NPP 4/04/2015 discontinuity 4/04/2015 experimental studies 4/04/2015 welded joint 4/04/2015 automated facility 4/04/2015 Integrated security system 4/04/2015 machine States 4/04/2015 network traffic 4/04/2015 Physical security 4/04/2015 specialized software 4/04/2015 standardized protocols 4/04/2015 the industry standard 4/04/2015 corrosion protection 4/04/2015 fuel element sublayer 4/04/2015 lead, magnesium 4/04/2015 zirconium nitride 4/04/2015 BN-6002 4/04/2015 computational and experimental studies 4/04/2015 cracks 4/04/2015 creep 4/04/2015 intermediate heat exchanger 4/04/2015 multi-cycle fatigue 4/04/2015 stress intensity factor 4/04/2015 stress strained state 4/04/2015 damage dose 4/04/2015 guide tubes 4/04/2015 temperature gradient 4/04/2015 dielectrics 4/04/2015 dose monitor 4/04/2015 optical studies 4/04/2015 radiation material science 4/04/2015 auxiliary power consumption 4/04/2015 consumer 4/04/2015 industrial object 4/04/2015 collector unit 4/04/2015 temperature state 4/04/2015 check valve 4/04/2015 check valve model 4/04/2015 hydro-dynamic force 4/04/2015 similarity criteria 4/04/2015 test facility 4/04/2015 high level waste 4/04/2015 immobilization 4/04/2015 matrix materials 4/04/2015 self-extending high-temperature synthesis 4/04/2015 inorganic ligands 4/04/2015 ion exchange 4/04/2015 liquid radwaste 4/04/2015 WWER-1000 4/04/2015 difference scheme 4/04/2015 the discrete ordinates method 4/04/2015 breeder 4/04/2015 BRIG 300 4/04/2015 cartogram 4/04/2015 dissociating coolant 4/04/2015 nitrin 4/04/2015 TRIGEX 4/04/2015 JEFF-3.11 4/04/2015 JENDL-4.0 4/04/2015 radioactive decay data library 4/04/2015 uncertainties 4/04/2015 ionization chamber with 252Cf neutron source 4/04/2015 scintillation detector of neutrons 4/04/2015 uneutron spectrum 4/04/2015 acoustic-emission method 12/29/2014 data base 12/29/2014 data collection unit 12/29/2014 data storage unit 12/29/2014 preamplifier 12/29/2014 signal shape 12/29/2014 thermal shock 12/29/2014 hierarchical structure 12/29/2014 information noise 12/29/2014 on-screen presentation of information 12/29/2014 reporting 12/29/2014 loop channel 12/29/2014 reactor test 12/29/2014 thermionic 12/29/2014 thermionic fuel element 12/29/2014 burnt lime 12/29/2014 calcium oxide 12/29/2014 liquid sodium glass 12/29/2014 target activation 12/29/2014 experimental fuel assembly 12/29/2014 gamma emission 12/29/2014 gamma quantum 12/29/2014 radiation heat rate 12/29/2014 coolant flow hydrodynamics 12/29/2014 coolant flow mass transfer 12/29/2014 floating power unit 12/29/2014 flow friction coefficients 12/29/2014 fuel assemblies 12/29/2014 denaturation 12/29/2014 nonproliferation 12/29/2014 SVBR 100 12/29/2014 activation products 12/29/2014 corundum 12/29/2014 graphite stacking 12/29/2014 one-stage process 12/29/2014 radionuclide leaching velocity 12/29/2014 titanium carbide 12/29/2014 transuranium elements 12/29/2014 Y-Al-garnet 12/29/2014 fuel cycles 12/29/2014 minor actinides accumulation 12/29/2014 nuclear energy systems 12/29/2014 plutonium recycle 12/29/2014 VVER-TOI 12/29/2014 131I production 12/29/2014 cladding failure 12/29/2014 leakage tests 12/29/2014 leaking fuel rods 12/29/2014 post-irradiation examinations 12/29/2014 secondary degradation 12/29/2014 tellurium target 12/29/2014 visual inspection 12/29/2014 blanket 12/29/2014 high density of neutron flux 12/29/2014 neutron absorption cross-section 12/29/2014 thermonuclear facility 12/29/2014 bioindication 12/29/2014 fluctuating asymmetry 12/29/2014 morphological alterations 12/29/2014 pollen fertility 12/29/2014 explosive mixture 7/14/2014 radiation monitoring system 7/14/2014 radioactive corrosion products 7/14/2014 vessel-type boiling water reactor (BWR) 7/14/2014 thermal hydraulic code 7/14/2014 measurement system 7/14/2014 multi-point acoustic probe 7/14/2014 passive system of shut-down cooling of reactor 7/14/2014 volume gas content 7/14/2014 aluminum oxide aero-gel 7/14/2014 alumophosphate binding 7/14/2014 ceramics 7/14/2014 clamp material 7/14/2014 crystallization 7/14/2014 irradiated nuclear fuel 7/14/2014 liquid metals 7/14/2014 magnesium oxide 7/14/2014 nanostructured material 7/14/2014 silicon carbide 7/14/2014 silicon nitride 7/14/2014 zirconium dioxide 7/14/2014 аerogel 7/14/2014 activity calculation 7/14/2014 irradiated materials 7/14/2014 reaction cross-sections 7/14/2014 admissible thickness of piping 7/14/2014 radiation therapy 7/14/2014 radiation treatment planning 7/14/2014 service life 7/14/2014 strenght 7/14/2014 distribution of deposition 7/14/2014 calculation uncertainty 7/14/2014 GRS-method 7/14/2014 keff 7/14/2014 MMK 7/14/2014 BNAN-RF 7/14/2014 criticality 7/14/2014 RUSFOND 7/14/2014 covariance matrix 7/14/2014 fast reactor model 7/14/2014 neutron data 7/14/2014 branching process 7/14/2014 degeneration probability 7/14/2014 fission process 7/14/2014 neutron population 7/14/2014 nuclear accident 7/14/2014 self'sustaining fission chain reaction 7/14/2014 uncontrolled reactor power excursion due to prompt neutrons 7/14/2014 cladding temperature evaluation 7/14/2014 fuel element bundle models 7/14/2014 fuel subassemblies 7/14/2014 inter-channel exchange 7/14/2014 sodium cooled fast reactors 7/14/2014 statistics-modified model 7/14/2014 Automated Process Control System (APCS) 7/14/2014 hardware and software package 7/14/2014 process control systems 7/14/2014 technological parameters 7/14/2014 training laboratory 7/14/2014 strategy for transformation of a nuclear power engineering complex 5/29/2014 the closed nuclear fuel cycle 5/29/2014 the large-scale nuclear power engineering 5/29/2014 calculation programs 5/29/2014 collector 5/29/2014 coolant stratification 5/29/2014 crisis of heat transfer 5/29/2014 heat-exchange equipments 5/29/2014 hydraulic friction factor 5/29/2014 interchannel exchange 5/29/2014 liquid metal coolants 5/29/2014 methods of calculations 5/29/2014 thermohydraulic 5/29/2014 and thermal reactors 5/29/2014 atomic industry 5/29/2014 chemical manufacture 5/29/2014 direct-contact technology 5/29/2014 enriched uranium 5/29/2014 heat pipes 5/29/2014 innovative technology 5/29/2014 lyophobic capillary-porous systems 5/29/2014 metallurgy 5/29/2014 nanostructured oxides and aerogels 5/29/2014 plasma chemical synthesis of multifunctional nanostructured coating 5/29/2014 sweet water 5/29/2014 syngas 5/29/2014 water vapour 5/29/2014 computational domain 5/29/2014 heat sinks 5/29/2014 heat-releasing layer 5/29/2014 molten fuel 5/29/2014 vessel of reactor 5/29/2014 bundle of elastic rods 5/29/2014 dispersion media 5/29/2014 dynamic density 5/29/2014 heterogeneous media 5/29/2014 shell 5/29/2014 vibroacoustic dynamics 5/29/2014 multi-physics code 5/29/2014 thermal hydrolics 5/29/2014 thermal mechanics 5/29/2014 air heat exchanger 5/29/2014 bundle of finned tubes 5/29/2014 emergency cooling system 5/29/2014 experimental researches 5/29/2014 explicit knowledge 5/29/2014 fast breeder reactors 5/29/2014 fuel balance 5/29/2014 Global Nuclear Energy 5/29/2014 heavy water reactors 5/29/2014 implicit knowledge 5/29/2014 intellectual results 5/29/2014 knowledge dissemination 5/29/2014 knowledge transfer and preservation 5/29/2014 light water reactors 5/29/2014 nuclear fuel cycle modelling 5/29/2014 synergy 5/29/2014 solid-phase method 5/29/2014 aerodynamic facility V-2 5/29/2014 air heat exchanger (AHX) 5/29/2014 cross flow 5/29/2014 emergency heat removal system (EHRS) 5/29/2014 experimental study 5/29/2014 finned tube assembly 5/29/2014 measuring complex 5/29/2014 spiral finned tubes 5/29/2014 effective vapour pressure 5/29/2014 evaluation nuclear data files 5/29/2014 evaporation 5/29/2014 thermodynamic activity coefficient 5/29/2014 accuracy 5/29/2014 activity 5/29/2014 calculations 5/29/2014 constant data 5/29/2014 influence 5/29/2014 programs 5/29/2014 sodium reactor 5/29/2014 irradiated fuel 5/11/2014 account code 5/11/2014 reactor control and protection system 5/11/2014 RELAP 5/11/2014 transitional process 5/11/2014 data analysis (algorithms and implementation) 5/11/2014 distribution theory and Monte-Carlo studies 5/11/2014 measurement and error theory 5/11/2014 codes for dose and temperature computation 5/11/2014 radiation therapy planning 5/11/2014 radionuclide vertebroplasty 5/11/2014 synergism of irradiation and heating at bone cement polimerization 5/11/2014 voxel models 5/11/2014 anionic surface-active substances (ASAS) 5/11/2014 experimental irradiation channel 5/11/2014 experimental reactor 5/11/2014 experimental testbed 5/11/2014 liquid radioactive wastes 5/11/2014 sludge 5/11/2014 sorption purification 5/11/2014 synthetic detergents 5/11/2014 thermohydraulic characteristics of experimental channel 5/11/2014 WWR-c 5/11/2014 235U and 239Pu content assessment 5/11/2014 helium counter tube 5/11/2014 neutron spectrum analysis 5/11/2014 residence time 5/11/2014 transmission 5/11/2014 benchmark experiments 5/11/2014 evaluated neutron data library 5/11/2014 ICSBEP 5/11/2014 international handbooks 5/11/2014 IRPhEP 5/11/2014 characteristic function 5/11/2014 moments of distribution 5/11/2014 stochastic differential equations 5/11/2014 white noise 5/11/2014 zero power nuclear reactor 5/11/2014 burnable poison 5/11/2014 low power reactors 5/11/2014 reactor physics 5/11/2014 calculation code ROK/B 1/01/0001 code ROK/B 1/01/0001 ENDF/B-7 1/01/0001 EUCLID/V1 1/01/0001 Jπ = (3/2)+ state of the 5He and 5Li 1/01/0001 KORSAR/GP 1/01/0001 OECD/NEA test 1/01/0001 SOCRAT/V1 1/01/0001 solid/liquid/gaseous waste management 1/01/0001
English
Русский