155 results on '"Fomichenko, P. A."'
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2. Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package
3. Peculiarities of Changes in the Isotopic Composition of Pilot Fuel Elements of a VVER-SKD Reactor under Successive Irradiation in a Fast and Thermal Neutron Spectrum
4. Improving the accuracy of determining corrosion products in reinforced concrete structures by atomic emission spectrum analysis
5. Analysis of fuel cycle scenarios for a two-unit SCWR NPP
6. The Concept of a Nuclear Power Unit on the Basis of a Low-Power Multipurpose Test Research Reactor with Supercritical Light-Water Coolant
7. ДІАГНОСТИКА ФІНАНСОВОГО СТАНУ МАШИНОБУДІВНОГО ПІДПРИЄМСТВА НА ОСНОВІ ВИКОРИСТАННЯ НЕЙРОМЕРЕЖЕВОГО МОДЕЛЮВАННЯ
8. Features of Sport Achievement Motivation in Youth Football Players
9. Development of Reduced 3D Models for Neutronic Calculations of the ASTRA Critical Facility
10. Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor
11. New Stage in Russia’s Nuclear Energy Strategy
12. BASIC FEATURES OF TRANSLATION OF PROFESSIONALLY-ORIENTED TEXT IN THE FIELD OF ENERGY INDUSTRY (AS BASED ON THE ENGLISH LANGUAGE MATERIAL)
13. Software Verification for Techno-Economic Simulation of Nuclear Energy Systems: Results and Recommendations
14. USE OF AUTHENTIC FILMS WITH SUBTITLES IN THE PROCESS OF LEARNING NEW VOCABULARY IN HIGHER EDUCATION SECTOR (AS BASED ON THE ENGLISH LANGUAGE MATERIAL)
15. Analysis of the Effect of Restrictions on Isotopes 232,234,236U in Marketable LEU on the Choice of Methods for Enriching Reprocessed Uranium in Cascades of Centrifuges
16. Axial Distributions of Fission Reaction Rates in the Annular Core of the ASTRA Critical Facility with Poison Profiling Elements in the Internal Reflector
17. NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors
18. Security of Export Deliveries of Regenerated-Uranium Light-Water Reactor Fuel from the Standpoint of IAEA Safeguards
19. SPECIFICS OF HIGHER EDUCATION STUDENTS’ USE OF MACHINE TRANSLATION (AS BASED ON THE ENGLISH LANGUAGE MATERIAL)
20. Efficiency Assessment of Nuclear Energy Development Scenarios for Russia Using Multi-Criteria Analysis
21. Assessment of the level of business readiness for digitalization using marketing and neural network technologies
22. The influence of interaction in the «teacher-pupil» system on schoolchildren’s learning and development (based on foreign publications)
23. INVESTMENT COOPERATION AND PRODUCTION COOPERATION OF UKRAINE AND THE EU
24. On a Strategy for the Development of Nuclear Power in Russia
25. Method of Performing Uncertainty Analysis Using Neutron Covariance Data for HTGR
26. The Managerial Technologies of Communicative Management
27. Teacher-Student Relationships as a Factor of Successful Learning Activity in Schoolchildren
28. Possibility of Increasing the Number of Experimental Channels in VVR-Ts by Changing the Core Design
29. Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor
30. A method for development of efficient 3D models for neutronic calculations of ASTRA critical facility using experimental information
31. Specific Character of Loan-Words Perception in Youth Ethnic Culture
32. Influence of 236U on the Efficacy of Recycling Regenerated Uranium in VVER Fuel
33. Preliminary Computational Analysis of Reactivity Effects Due to Heating of the Astra Critical Stand
34. Two-dimensional equations of the surface harmonics method for solving problems of spatial neutron kinetics in square-lattice reactors
35. Implementation of Competence Approach with Simulation Technology
36. Equations of the surface harmonics method for solving time-dependent neutron transport problems and their verification
37. Evaluation of isotopic composition of fast reactor core in closed nuclear fuel cycle
38. ANALYSIS OF THE COMPETITIVENESS OF A NEW GENERATION BN POWER UNIT PROJECT, TAKING INTO ACCOUNT SYSTEM REQUIREMENTS
39. An investigation of some models and approximations used in calculating fuel assemblies of a high-temperature gas-cooled reactor of the GT-MHR type
40. Profiling of energy deposition fields in a modular HTHR with annular core: Computational/experimental studies at the ASTRA critical facility
41. Computational and experimental investigations of the neutron-physical characteristics of the GT-MHR core
42. Prospects for the development of a direct-flow vessel reactor with superheated steam
43. Optimization of Conceptual Solutions for the RBETs-M Lead–Bismuth Fast Reactor
44. Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility
45. Computational analysis of experiments to determine the kinetic parameters at the ASTRA HTGR type critical facility
46. Homogenised group constants generation using Monte Carlo codes for diffusion calculation of pebble bed reactor
47. Development of Fast Helium Reactors in Russia
48. MARS Low-Power Liquid-Salt Micropellet-Fuel Reactor
49. INFLUENCE OF MANUFACTURING UNCERTAINTIES ON HTGR NEUTRON PHYSICS AND FUEL ISOTOPIC COMPOSITION DURING BURNUP
50. Analysis of the Effect of Restrictions on Isotopes 232,234,236U in Marketable LEU on the Choice of Methods for Enriching Reprocessed Uranium in Cascades of Centrifuges.
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