Персона:
Гераскин, Николай Иванович

Научные группы

Научная группа

Лаборатория инновационных ядерных реакторов и ядерных топливных циклов (Кафедра №5 ИЯФиТ)

Организационные подразделения

Организационная единица

Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.

Фамилия

Гераскин

Имя

Николай Иванович

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Теперь показываю 1 - 10 из 26

Только метаданные
Evaluating Conditions and Possibilities for Neutron Catalysis of Thermonuclear Reactions in Three-Component (D–T–3He)-Plasma
(2022) Shmelev, A. N.; Geraskin, N. I.; Apse, V. A.; Glebov, V. B.; Kulikov, G. G.; Kulikov, E. G.; Гераскин, Николай Иванович; Апсэ, Владимир Александрович; Глебов, Василий Борисович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
Только метаданные
The knowledge preservation problem in the nuclear industry and the role of Web-based tools in its solution
(2019) Geraskin, N. I.; Kulikov, E. G.; Glebov, V. B.; Гераскин, Николай Иванович; Куликов, Евгений Геннадьевич; Глебов, Василий Борисович
© The Author(s) 2019.This case study analyses an application of distance training in the practice of nuclear knowledge preservation. The purpose of the research is to evaluate the potential of distance training in solving the problem of knowledge preservation in the nuclear industry. Thirty specialists from different European countries participated in the pilot training experiments. It was found that the efficacy of distance training depends directly on the convenience and ease of the knowledge transmission process, the possibility for the trainees to combine training with their professional activities, the ability to work independently and a conscious desire on the part of trainees to improve their professional competencies. The study included a comprehensive evaluation of the distance training platform Cyber Learning Platform for Network Education and Training (CLP4NET) in the context of nuclear knowledge preservation. It was found that CLP4NET provided a friendly interface, was relatively easy to use and allowed an extensive application of interactive data representation forms and ample communication between training participants.
Только метаданные
Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR
(2020) Shchurovskaya, M. V.; Geraskin, N. I.; Kruglikov, A. E.; Щуровская, Мария Владимировна; Гераскин, Николай Иванович; Кругликов, Антон Евгеньевич
© 2020 Elsevier LtdIn this study, we analyze different methods for the generation of homogenized few-group cross sections (XS) using continuous-energy Monte Carlo codes Serpent 2.1.29 and MCU–PTR for full-core diffusion calculation of small-size light water research reactors. Few-group reaction cross sections, scattering matrices and diffusion coefficients generated in an infinite lattice model with and without B1-leakage correction of spectra, and in full-scale 3D core calculations, are compared. Few-group XS are used in the TIGRIS diffusion nodal simulator to calculate the simplified cores with IRT-3 M fuel and a light water reflector. Special attention is paid to the impact of diffusion coefficients on the results of diffusion calculations. We compare the following different methods for the generation of diffusion coefficients: the usual “out-scatter” approximation, the transport correction for hydrogen implemented in Serpent, and the migration method implemented in MCU–PTR.
Только метаданные
Network engineering education: Prospects for the implementation of the Worldwide CDIO Initiative in nuclear areas
(2020) Geraskin, N. I.; Krasnoborodko, A. A.; Glebov, V. B.; Гераскин, Николай Иванович; Краснобородько, Андрей Альбертович; Глебов, Василий Борисович
© The Author(s) 2020.This article summarises the results of a preliminary feasibility study and the experience of implementing Conceive-Design-Implement-Operate (CDIO) ideas during 2016–2019 in the education of nuclear specialists. The study is a form of empirical research. The results and findings regarding implementation of the CDIO approach are presented in relation to the Russia–Kazakhstan network programme of specialist training for the nuclear industry of Kazakhstan. The authors conclude that CDIO ideas effectively promote solutions to educational challenges facing the nuclear industries of specific countries. Key findings are (a) that the network form of education is well-suited to the implementation of the CDIO approach and (b) that the principle of the safe management of nuclear materials should be considered in the context of engineering education.
Только метаданные
Simulation-based studies on graphite absorption properties for ASTRA critical experiments
(2022) Nevinitsa, V. A.; Fomichenko, P. A.; Jitarev, V. E.; Shchurovskaya, M. V.; Kruglikov, A. E.; Volkov, Y. N.; Geraskin, N. I.; Щуровская, Мария Владимировна; Кругликов, Антон Евгеньевич; Волков, Юрий Николаевич; Гераскин, Николай Иванович
© 2022 Elsevier LtdThis work is focused on the improvement of the graphite impurity content characterization for the ASTRA critical facility. The equivalent boron content for the graphite reflectors of the ASTRA facility reported in the benchmark specifications was estimated using the results of the exponential experiments performed by graphite manufacturer. Because raw measured data are not available for these experiments, we tried to reassess the equivalent boron content for the ASTRA graphite reflectors using the results of analogous exponential experiments performed earlier on the empty RBMK critical facility at the National Research Center «Kurchatov Institute» and further simulation of the experiments utilizing the Monte Carlo code Serpent with ENDF/B-VII.0, ENDF/B-VII.1, and ENDF/B-VIII.0 cross-section libraries. The same grade graphite was used for manufacturing the graphite blocks for the RBMK critical facility and the ASTRA critical facility. The Monte Carlo simulations confirmed the accuracy of the exponential measurements performed for RBMK graphite characterization. It was also shown that the simulation must reproduce the graphite absorption cross-section estimated using the exponential experiments for the agreement between the measured and calculated distribution of thermal neutron flux. Therefore, the equivalent boron content should be assessed individually for each cross-section library used in the simulation. In case of the ASTRA facility the carbon capture cross section of 3.36 mb at 0.0253 eV (ENDF/B-VII.0) was used to deduce the equivalent boron content of 1 ppm wt from the measured results. Thermal capture cross-section of carbon was significantly increased in the ENDF/B-VII.1 and other recent cross-section libraries. Therefore, when calculating the ASTRA benchmark with these cross-section libraries the equivalent boron content reported in the benchmark specification should be reassessed.
Только метаданные
Comprehensive analysis of ASTRA benchmark with MCU-HTR and Serpent codes
(2024) Kruglikov, A. E.; Shchurovskaya, M. V.; Volkov, Yu. N.; Geraskin, N. I.; Кругликов, Антон Евгеньевич; Щуровская, Мария Владимировна; Волков, Юрий Николаевич; Гераскин, Николай Иванович
Только метаданные
Application of Minor Actinides for the Large-Scale Production of 238Pu in a Supercritical Light-Water Reactor
(2023) Shmelev, A. N.; Geraskin, N. I.; Apse, V. A.; Glebov, V. B.; Kulikov, G. G.; Kulikov, E. G.; Гераскин, Николай Иванович; Апсэ, Владимир Александрович; Глебов, Василий Борисович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
Открытый доступ
Nuclear education in Russia and abroad Ядерное образование в России и в зарубежных странах
(2019) Volkov, Y. N.; Geraskin, N. I.; Kosilov, A. N.; Волков, Юрий Николаевич; Гераскин, Николай Иванович; Косилов, Андрей Николаевич
© 2019 Moscow Polytechnic University. All rights reserved.The education of a future nuclear professional provides the basic competencies that will influence the performance of a future specialist throughout his or her future professional career. The article discusses the best practices and main trends in higher education that have developed in the field of nuclear technologies in Russia and abroad. The analysis is based on the materials prepared by various international organizations and professional communities, and the experience of the MEPhI. The article discusses such issues as interaction between state, nuclear industry and higher education institution; the quality of nuclear education (four basic principles of training nuclear specialists in MEPhI), the transition to two-tier system in nuclear education; the international cooperation in nuclear sphere; export of nuclear education; and vocational guidance for school students.
Только метаданные
Thermonuclear Plasma Model with Bound Ions and Neutron Catalysis of Fusion Reactions
(2022) Shmelev, A. N.; Geraskin, N. I.; Apse, V. A.; Glebov, V. B.; Kulikov, G. G.; Kulikov, E. G.; Гераскин, Николай Иванович; Апсэ, Владимир Александрович; Глебов, Василий Борисович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
Только метаданные
Using the Am Fraction of Minor Actinides for the Production of Plutonium Suitable for Radioisotope Thermoelectric Generators
(2023) Shmelev, A. N.; Geraskin, N. I.; Apse, V. A.; Glebov, V. B.; Kulikov, G. G.; Kulikov, E. G.; Kruglikov, A. E.; Гераскин, Николай Иванович; Апсэ, Владимир Александрович; Глебов, Василий Борисович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич; Кругликов, Антон Евгеньевич