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Your search keyword '"Fomichenko, P. A."' showing total 153 results
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153 results on '"Fomichenko, P. A."'

22. Leakage control of HTGR fuel using a weak irradiation technique.

Author

Agulnik, M. A., Grol, A. V., Degtyarev, V. V., Kondratieva, E. S., Fomichenko, P. A., Reshetnikov, A. A., Fedin, O. I., Chumak, L. G., Beleevskiy, A. V., Golubev, I. E., and Davydov, A. V.

Abstract

Radiation safety of high temperature gas-cooled reactors (HTGRs) largely depends on the leakage of fission products from the fuel under both normal and emergency modes of operation. Within the development of a pilot industrial fuel technology for an HTGR of the nuclear power engineering plant, we conducted pre-reactor tests of laboratory manufactured fuel to determine the leakage of fission products, as well as to assess the contamination of structural materials with uranium. Bulk TRISO particles, TRISO particle compacts, and blank graphite compacts were studied. The conducted tests used a weak irradiation technique developed by the NRC "Kurchatov Institute". The technique is based on measuring the leakage of gaseous fission products from weakly irradiated samples during their annealing at temperatures close to the core temperature. A small dose of radiation causes no effect on the basic initial physical and chemical properties of fuel (density, porosity, etc.), as well as the ability to retain fission products. We analyzed the quality of laboratory-manufactured HTGR fuel by comparing the measured relative leakage of reference radionuclides with the established permissible limits, including individual technological stages of production. The study highlights the importance of the technique for quality control of HTGR fuel. [ABSTRACT FROM AUTHOR]

Published
2025
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33. ANALYSIS OF THE COMPETITIVENESS OF A NEW GENERATION BN POWER UNIT PROJECT, TAKING INTO ACCOUNT SYSTEM REQUIREMENTS

Author

Alekseev, P, primary, Andrianov, A, primary, Bakanov, M, primary, Balanin, A, primary, Gulevich, A, primary, Dekusar, V, primary, Egorov, A, primary, Korobeinikov, V, primary, Marova, E, primary, Maslov, A, primary, Moseev, A, primary, Nevinitsa, V, primary, Teplov, P, primary, Farakshin, M, primary, Fomichenko, P, primary, and Shepelev, S, primary

Published
2021
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41. 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.

Author

Smirnov, A. Yu., Gusev, V. E., Sulaberidze, G. A., Nevinitsa, V. A., and Fomichenko, P. A.

Subjects
URANIUM isotopes, URANIUM, ISOTOPES, CENTRIFUGES, ISOTOPE separation, URANIUM enrichment, PROBLEM solving
Abstract

The study addresses the problems of reprocessed uranium re-enrichment. It is shown that, in the most general formulation, the problem of reprocessed uranium re-enrichment that meets all the requirements on the content of even isotopes and the conditions of spending a given amount of initial reprocessed uranium for production of unit mass of the product cannot be solved in a three-flow cascade of centrifuges or in the simplest versions of double cascades. The possibility of solving the formulated problem in a modified double cascade scheme with a low-enriched uranium (LEU) diluter is demonstrated. The results of numerical experiments showed that it is possible to obtain marketable LEU in the studied version of the double cascade after spending a given amount of reprocessed uranium and meeting different constraints on 232U concentration in the product, including even stricter constraints than those currently accepted at separation plants. [ABSTRACT FROM AUTHOR]

Published
2021
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44. MULTI-CRITERIA ASSESSMENT OF COMPETITIVENESS OF THE BN-TYPE COMMERCIAL POWER UNIT IN THE RUSSIAN ENERGY SYSTEM

Author

Alekseev, P, primary, Blandinsky, V, primary, Balanin, A, primary, Grol, A, primary, Gulevich, A, primary, Dekusar, V, primary, Egorov, A, primary, Korobeinikov, V, primary, Marova, E, primary, Maslov, A, primary, Moseev, A, primary, Nevinitsa, V, primary, Teplov, P, primary, Farakshin, M, primary, Fomichenko, P, primary, Shepelev, S, primary, and Shirokov, A, primary

Published
2019
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46. THE SYSTEM OF EVALUATING THE EFFECTIVENESS OF EMPLOYEES MOTIVATION AS A FACTOR OF THE ENTERPRISE SUSTAINABLE DEVELOPMENT

Author

Korytko, Tetyana, Piletska, Samira, Arefieva, Olena, Pidhora, Yelizoveta, and Fomichenko, Inna

Abstract

An important prerequisite for the development of modern society in the maximum use of innovations is the special attention of the personnel, which creates conditions for economic growth and competitiveness of both the individual employee and the company as a whole, as well as guarantees its economic security. In addition to certain labor conditions at an industrial enterprise, each employee has his/her own personal motives and incentives that motivate him/her to perform the tasks assigned to him on a daily basis. In this regard, the purpose of this research is to develop methodological frameworks for evaluating the effectiveness of the employees’ incentives system to increase the intellectualization of the enterprise and identify priority areas for improving their coordination to ensure the sustainable economic development. The article formulates criteria for evaluating the effectiveness of the employees’ incentives system for to increase the intellectualization of the enterprise, which include indicators of balance, resource intensity, social activity etc. On the basis of the specified indicators the evaluation of efficiency of the employees’ incentives system to increase the enterprise intellectualization is carried out and measures for stimulation of employees to the further development of the enterprise are developed.

Published
2021
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50. Method of Performing Uncertainty Analysis Using Neutron Covariance Data for HTGR.

Author

Grol', A. V., Boyarinov, V. F., and Fomichenko, P. A.

Subjects
ABSORPTION cross sections, NEUTRONS, DATA libraries, UNCERTAINTY, CORRECTION factors, NEUTRON transport theory
Abstract

The aim of this work is to develop methods for calculating the neutronic parameters of HTGR and to perform uncertainty analysis with the aid of design programs and neutron covariance data. The method and software modules for preparing multigroup libraries of covariance data for individual isotopes based on a 44-group library of covariance data of the SCALE-6 computational complex were improved in the course of this work. Correction factors are introduced to improve the accuracy of the method. The WIMSD-5 code with a 69-group cross-section libraries, created on the basis of ENDF/BVII.0 and ENDF/BVII.1 evaluated nuclear data files, is used for the neutronic calculations. Calculations of the uncertainties of one-group fission and absorption cross sections for the main isotopes of the elements of the MHTGR-350 core as well as the neutron multiplication coefficients for the fuel-compact cells and fuel-block cells of the MHTGR-350 reactor were performed to verify the developed method. [ABSTRACT FROM AUTHOR]

Published
2019
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