Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Vladimir Nikolaevich Nesterov"'
FORECASTING POTENTIAL RISKS OF URBAN CONSTRUCTION IN THE TASKS OF STRATEGIC AND TERRITORIAL PLANNING
Publikováno v:
Региональные аспекты развития науки и образования в области архитектуры, строительства, землеустройства и кадастров в начале III тысячелетия. Материалы Международной научно-практической конференции.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8172822fc5878b44fbcd23838c89ab19
https://doi.org/10.17084/978-5-7765-1471-5-2022-189
https://doi.org/10.17084/978-5-7765-1471-5-2022-189
Autor:
Vladimir Nikolaevich Nesterov, Anatoly Andreevich Prets, Igor V. Shamanin, Igor O. Lutsik, Sergej Vladimirovich Bedenko
Publikováno v:
Nuclear Energy and Technology, Vol 4, Iss 1, Pp 79-85 (2018)
Nuclear Energy and Technology 4(1): 79-85
Nuclear Energy and Technology 4(1): 79-85
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::71614255caf3aac5d34aeeebc2c6423d
https://nucet.pensoft.net/article/29837/
https://nucet.pensoft.net/article/29837/
Autor:
Igor’ Vladimirovich Shamanin, Sergej Vladimirovich Bedenko, Vladimir Nikolaevich Nesterov, Igor Olegovich Lutsik, Anatoly Andreevich Prets
Publikováno v:
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika. 2017:38-49
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dab1acb31e5e99ad088314c94c816527
https://doi.org/10.26583/npe.2017.4.04
https://doi.org/10.26583/npe.2017.4.04
Autor:
Olga Igorevna Bulakh, Oleg Konstantinovich Kostylev, Vladimir Nikolaevich Nesterov, Eldar Koshalievich Cherdizov
Publikováno v:
Nuclear Energy and Technology 5(4): 289-295
Nuclear Energy and Technology, Vol 5, Iss 4, Pp 289-295 (2019)
Nuclear Energy and Technology, Vol 5, Iss 4, Pp 289-295 (2019)
High-temperature gas-cooled reactor (HTGR) is one of promising candidates for new generation of nuclear power reactors. This type of nuclear reactor is characterized with the following principal features: highly efficient generation of electricity (t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::db6b2a9df0f32103102df748702663f0
https://doi.org/10.3897/nucet.5.48391
https://doi.org/10.3897/nucet.5.48391
Publikováno v:
Nuclear Energy and Technology, Vol 2, Iss 3, Pp 183-190 (2016)
The paper describes a method for determining the effective neutron multiplication factor and the breeding ratio for the KLT-40S at operating conditions. The main reactor design features are presented which are necessary for calculations. It is shown
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e3b79bb9e2db3b2fe05e489cd9fab360
https://doi.org/10.1016/j.nucet.2016.07.008
https://doi.org/10.1016/j.nucet.2016.07.008
Autor:
Alexei Valerievich Godovykh, Denis Fyodorovich Baybakov, Igor’ Sergeevich Martynov, Vladimir Nikolaevich Nesterov
Publikováno v:
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika. 2016:99-111
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d1e4c173ac00a2a6a04b3c44275b45c
https://doi.org/10.26583/npe.2016.2.10
https://doi.org/10.26583/npe.2016.2.10
Autor:
Sergei V. Beliavskii, Roman Laas, Olga Igorevna Bulakh, Vladimir Nikolaevich Nesterov, Alexei V. Godovikh
Publikováno v:
Nuclear Engineering and Design. 360:110524
Fuel lifetime is a crucial parameter for small reactors used as the main part of floating power plants. Such plants have the potential to solve energy supply problems of remote regions. This article explains the methodology used to determine the effe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ebbfb948c6359219b4d034a8016cf312
https://doi.org/10.1016/j.nucengdes.2020.110524
https://doi.org/10.1016/j.nucengdes.2020.110524
Autor:
Vladimir Nikolaevich Nesterov, Artyom Georgievich Najmushin, Aleksandr Mihajlovich Mochalov, Dmitrij Konstantinovich Pugachyov
Publikováno v:
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika. 2015:101-110
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::32f7a00ebcff4bb4038e67ad6d4604ba
https://doi.org/10.26583/npe.2015.4.11
https://doi.org/10.26583/npe.2015.4.11
Autor:
Artem Naymushin, Aleksey V. Golovatsky, Savva N. Savanyuk, Denis Fyodorovich Baybakov, Igor V. Shamanin, Vladimir Nikolaevich Nesterov
Publikováno v:
Advanced Materials Research. 1084:313-316
This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graph
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ecfd28b6454d05601a49b7629f1c9420
https://doi.org/10.4028/www.scientific.net/amr.1084.313
https://doi.org/10.4028/www.scientific.net/amr.1084.313
Autor:
Igor Shamanin, Denis Fyodorovich Baybakov, Sevastyan Savanuk, Artem Naymushin, Vladimir Nikolaevich Nesterov
Publikováno v:
Advanced Materials Research. 1084:294-297
This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal prop
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a3cb5b786228733e71965abfe6cdbb9d
https://doi.org/10.4028/www.scientific.net/amr.1084.294
https://doi.org/10.4028/www.scientific.net/amr.1084.294