Zobrazeno 1 - 10
of 43
pro vyhledávání: '"V. A. Nevinitsa"'
Publikováno v:
Глобальная ядерная безопасность, Vol 0, Iss 2, Pp 5-19 (2024)
The MTIR-SCP reactor is a research reactor with a light-water coolant having a fast neutron spectrum in nominal operation. None of the existing or projected reactors has a set of these features, therefore, special attention should be paid to the choi
Externí odkaz:
https://doaj.org/article/7072293f7dcf4f499315804c01aa910d
Autor:
A. A. Sedov, V. Yu. Blandinskii, Ya. A. Kotov, D. S. Kuzenkova, A. S. Lapin, V. A. Nevinitsa, S. B. Pustovalov, A. S. Stepanov, S. A. Subbotin, P. A. Fomichenko, B. I. Fonarev, A. A. Frolov
Publikováno v:
Thermal Engineering. 70:323-338
Publikováno v:
Journal of Engineering Physics and Thermophysics. 96:547-554
Autor:
V. A. Nevinitsa, P. A. Fomichenko, V. F. Boyarinov, A. A. Zimin, A. E. Kruglikov, Yu. N. Volkov
Publikováno v:
Physics of Atomic Nuclei. 85:1383-1390
Publikováno v:
Physics of Atomic Nuclei. 84:1495-1499
Publikováno v:
Physics of Atomic Nuclei. 84:1500-1507
Autor:
V. A. Nevinitsa, V. F. Boyarinov, P. A. Fomichenko, A. A. Zimin, A. E. Glushkov, N. P. Moroz, Yu. N. Volkov, A. E. Kruglikov
Publikováno v:
Physics of Atomic Nuclei. 84:1397-1404
Autor:
V. F. Boyarinov, Yu. N. Volkov, A. E. Kruglikov, M N Zizin, V. A. Nevinitsa, P. A. Fomichenko
Publikováno v:
Kerntechnik. 85:4-8
Coupled neutronic and thermal hydraulic calculation codes are verified for calculating the design of modern and prospective types of nuclear reactors. This verification is done by comparing experimental and calculated results for stationary and trans
Autor:
A. Yu. Smirnov, V. Yu. Blandinskii, Yu. N. Volkov, G. A. Sulaberidze, V. E. Gusev, V. A. Nevinitsa, P. A. Fomichenko
Publikováno v:
Atomic Energy. 128:368-374
The nonproliferation of nuclear materials is the key issue in supplying nuclear fuel to foreign countries. This article discusses the use of regenerated uranium to enhance the security of exports of fresh fuel for light-water reactors. It is shown th
Autor:
I. A. Belov, A. Yu. Smirnov, E. A. Bobrov, V. E. Gusev, V. A. Nevinitsa, G. A. Sulaberidze, E. V. Rodionova
Publikováno v:
Atomic Energy. 128:223-231
Issues concerning fuel cycle closure are discussed. It is shown that from the standpoint of full utilization of reprocessed nuclear materials the main problems are associated with repeated recycling of uranium, the reason being that limitations are i