Zobrazeno 1 - 10
of 32
pro vyhledávání: '"N. I. Geraskin"'
Publikováno v:
Высшее образование в России, Vol 28, Iss 11, Pp 105-116 (2019)
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 hi
Externí odkaz:
https://doaj.org/article/b90fdb9586054b1397818f4e3cce6b0f
Publikováno v:
Высшее образование в России, Vol 0, Iss 6, Pp 101-107 (2017)
The article highlights the milestones of the formation and the current state of nuclear education at National Research Nuclear University MEPhI. The authors dwell on the activities of the Institute of nuclear physics and engineering, which concentrat
Externí odkaz:
https://doaj.org/article/1638b168907e48969e3077b573f07822
Publikováno v:
Physics of Atomic Nuclei. 85:1961-1965
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ccade4e054a6ba77891b59c1ba49e090
https://doi.org/10.1134/s106377882210057x
https://doi.org/10.1134/s106377882210057x
Publikováno v:
Physics of Atomic Nuclei. 85:1491-1496
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6504262cce81ae43d90ca898ac23f10
https://doi.org/10.1134/s1063778822090332
https://doi.org/10.1134/s1063778822090332
Autor:
Yu.B. Chertkov, M. V. Shchurovskaya, V. P. Alferov, A.I. Radaev, N. I. Geraskin, M.N. Anikin, I.I. Lebedev, A. Naymushin
Publikováno v:
Annals of Nuclear Energy. 113:436-445
This paper presents the results of the validation of the MCU-PTR code computational model of beryllium poisoning caused by 3 He and 6 Li buildup against selected experiments at the IRT-T research reactor in the National Research Tomsk Polytechnic Uni
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d72ccb5e026b85d7b65032d452436f38
https://doi.org/10.1016/j.anucene.2017.11.046
https://doi.org/10.1016/j.anucene.2017.11.046
Publikováno v:
Atomic Energy. 123:81-86
The results of an analysis of the radiological consequences of a beyond design basis accident for IRT MEPhI with high-enrichment uranium fuel and conversion to IRT-3M fuel assemblies with fuel kernel based the alloy U–9% Mo in an aluminum matrix wi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b182db7104974ab16968009062135f1
https://doi.org/10.1007/s10512-017-0305-1
https://doi.org/10.1007/s10512-017-0305-1
Autor:
V. P. Alferov, M.N. Anikin, I.I. Lebedev, A. Naymushin, A.I. Radaev, M. V. Shchurovskaya, N. I. Geraskin, Yu.B. Chertkov
Publikováno v:
Annals of Nuclear Energy. 96:332-343
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44160a66f89676f7f4678c57d8f09c6f
https://doi.org/10.1016/j.anucene.2016.06.015
https://doi.org/10.1016/j.anucene.2016.06.015
Autor:
A. F. Kozhin, A. V. Bushuev, T. B. Aleeva, R. R. Khalitov, N. I. Geraskin, V. N. Zubarev, V. S. Rudenko, E. M. Glagovskii
Publikováno v:
Atomic Energy. 120:44-47
One problem of decommissioning graphite reactors is the evaluation of the radioactive contamination of the graphite. The possible methods of determining the composition, contamination, and radionuclide concentration by means of laboratory analysis of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e12abb8ac2ec1583f2a24fa6ce490f3
https://doi.org/10.1007/s10512-016-0093-z
https://doi.org/10.1007/s10512-016-0093-z
Publikováno v:
Atomic Energy. 120:15-21
The results of calculations of emergency situations for the IRT MIFI [Moscow Engineering Physics Institute] reactor with high-enrichment uranium fuel and with conversion to IRT-3M fuel assemblies with fuel cores based on the alloy U–9%Mo in an alum
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9c1dcd8123231915af48926ebafe777f
https://doi.org/10.1007/s10512-016-0089-8
https://doi.org/10.1007/s10512-016-0089-8
Autor:
L. I. Yakovlev, A. B. Gaiduchenko, A. A. Serebryakov, A. E. Kruglikov, N. I. Geraskin, T. B. Aleeva, D. V. Andreev, S. A. Ozherelev, A. F. Kozhin, M. V. Shchurovskaya, V. P. Alferov
Publikováno v:
Journal of Physics: Conference Series. 1689:012024
Life cycle extension practices for U–Al fuel in Al cladding used at the OR and the IRT MEPhI research reactors are discussed. The IRT MEPhI reactor uses tube type IRT-3M FA with dispersed UO2–Al fuel meat and SAV–1 aluminum alloy as cladding. T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f05bc65335ee434c7e8abf3b3cf6593f
https://doi.org/10.1088/1742-6596/1689/1/012024
https://doi.org/10.1088/1742-6596/1689/1/012024