Zobrazeno 1 - 10
of 24
pro vyhledávání: '"E. F. Mitenkova"'
Publikováno v:
Atomic Energy. 131:212-218
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89e216c3c05e69a4cc7c5e25b5a489d9
https://doi.org/10.1007/s10512-022-00863-7
https://doi.org/10.1007/s10512-022-00863-7
Publikováno v:
Atomic Energy. 130:344-347
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb6c75a99b37d4dab13d21feea29c2ae
https://doi.org/10.1007/s10512-022-00822-2
https://doi.org/10.1007/s10512-022-00822-2
Publikováno v:
Atomic Energy. 128:171-176
The observed differences of the neutron fluxes between experiments and calculations on passage of neutrons through thick layers of iron and steel are conditioning the use of better models for representing the scattering cross-sections and energy-angl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9870fafb4c243cd8a18dcadca538d8db
https://doi.org/10.1007/s10512-020-00670-y
https://doi.org/10.1007/s10512-020-00670-y
Publikováno v:
Informacionnye Tehnologii. 26:231-238
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36333c5fd75ae891ca66b32a0aeaad73
https://doi.org/10.17587/it.26.231-238
https://doi.org/10.17587/it.26.231-238
Autor:
E. F. Mitenkova, T. V. Semenova
Publikováno v:
Atomic Energy. 126:16-20
The possibility of non-physical local neutron distributions in weakly coupled systems in Monte Carlo calculations of the criticality is engendering the development of new algorithms. New possibilities of the TDMCC code for calculating neutron distrib
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3bc8a84342e3dd5dd107c12dcf97524
https://doi.org/10.1007/s10512-019-00507-3
https://doi.org/10.1007/s10512-019-00507-3
Publikováno v:
Atomic Energy. 125:370-375
The BONUS model of the formation, radioactive interactions, and transport of fission products in nuclear fuel is modified to describe the behavior of hydrogen and helium in irradiated nuclear fuel as well as to accumulate an expanded list of transura
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a3f54522d212dcde803f2b9d141a7936
https://doi.org/10.1007/s10512-019-00496-3
https://doi.org/10.1007/s10512-019-00496-3
Publikováno v:
Atomic Energy. 124:69-73
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e1b0a380dd6c430eea77a34f5971d042
https://doi.org/10.1007/s10512-018-0377-6
https://doi.org/10.1007/s10512-018-0377-6
Autor:
E. F. Mitenkova, D. A. Koltashev
Publikováno v:
Atomic Energy. 125:139-141
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::460ab6133a1afb48dad59b0a04e4d702
https://doi.org/10.1007/s10512-018-0456-8
https://doi.org/10.1007/s10512-018-0456-8
Publikováno v:
Atomic Energy. 120:214-219
The mathematical modeling of nuclear fuel burnup is based on the solution of a system of ordinary differential equations of the Bateman type. The particularities of the systems obtained are examined. Examples of possible computational inaccuracies of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ce28386d942e5bcbddf44a8d4eb5e37
https://doi.org/10.1007/s10512-016-0120-0
https://doi.org/10.1007/s10512-016-0120-0
Publikováno v:
Physics of Atomic Nuclei. 78:1301-1308
The calculation method of neutron yield in the (α, n) reaction for a homogeneous material of arbitrary composition is represented. It is shown that the use of the ORIGEN 2 code excluding the real elemental composition of vitrified high-level waste l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c36ac4927bdfbc27884faf2cb8181d86
https://doi.org/10.1134/s106377881511006x
https://doi.org/10.1134/s106377881511006x