Research Output per year
Fingerprint Dive into the research topics where Arian Valerievich Kuzmin is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
- 21 Similar Profiles
Neutron flux
Engineering & Materials Science
Research reactors
Engineering & Materials Science
Thermal conductivity
Engineering & Materials Science
Samarium
Engineering & Materials Science
Uranium
Chemical Compounds
Neutrons
Engineering & Materials Science
Fast reactors
Engineering & Materials Science
Xenon
Engineering & Materials Science
Network
Recent external collaboration on country level. Dive into details by clicking on the dots.
Research Output 2000 2017
Analytical estimation of the central reflector impact on thermal and fast neutron flux density in research reactors
Gvozdyakov, D. V., Kuzmin, A. V., Tanishev, A. O. & Shvab, S. A., 21 Mar 2017, Proceedings - 2016 11th International Forum on Strategic Technology, IFOST 2016. Institute of Electrical and Electronics Engineers Inc., p. 612-614 3 p. 7884335. (Proceedings - 2016 11th International Forum on Strategic Technology, IFOST 2016).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
Research reactors
Neutron flux
Reflector
Neutron
Reactor
Effective fuel temperature of wwer-1000
Kudrov, A., Kuzmin, A. & Rakov, Y., 19 Jun 2017, In : MATEC Web of Conferences. 110, 01046.Research output: Contribution to journal › Conference article
Open Access
Thermal conductivity
Uranium
Pressurized water reactors
Temperature
Temperature distribution
Neutron Age Determination in Fast Reactor Materials using the Group Method
Kabanova, M. F., Yuzhakov, A. V., Kuzmin, A. V., Kobenko, Y. V. & Riabova, E. S., 9 Aug 2016, In : MATEC Web of Conferences. 72, 01040.Research output: Contribution to journal › Conference article
Open Access
Fast reactors
Neutrons
Uranium
Nuclear reactors
Coolants
1
Citation
(Scopus)
Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry
Kuzmin, A. V. & Yurkov, M. M., 21 Dec 2016, In : MATEC Web of Conferences. 92, 01050.Research output: Contribution to journal › Conference article
Open Access
Stoichiometry
Thermal conductivity
Uranium dioxide
uranium dioxide
4
Citations
(Scopus)
Analytical estimation of the central reflector impact on thermal neutron flux density in research reactors
Gvozdyakov, D. V., Tanishev, A. O., Shvab, S. A., Martyshev, V. N. & Kuzmin, A. V., 22 Dec 2015, In : MATEC Web of Conferences. 37, 01024.Research output: Contribution to journal › Conference article
Open Access
Research reactors
Neutron flux
Hot Temperature