Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Dmitry Yu. Tomashchik"'
Autor:
Juri Stuckert, Ch. Bals, T. Hollands, H. Austregesilo, T. A. Yudina, Dmitry Yu. Tomashchik, A. E. Kiselev
Publikováno v:
Nuclear Engineering and Design. 342:320-335
Analyses of the CORA-15 bundle test have been performed with the system codes ATHLET-CD (GRS) and SOCRAT (IBRAE). In the test, the behaviour of a PWR type fuel bundle, composed of 23 fuel rods and 2 absorber rods, was investigated under severe accide
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eff3a659e42db80d83f66073d7856b37
https://doi.org/10.1016/j.nucengdes.2018.12.015
https://doi.org/10.1016/j.nucengdes.2018.12.015
Autor:
Vladimir N. Blinkov, Oleg I. Melikhov, Vladimir I. Melikhov, Andrey V. Kapustin, Kirill S. Dolganov, Dmitry Yu. Tomashchik, Vladimir N. Semenov, Artem E. Tarasov, Sergey S. Selkin
Publikováno v:
Nuclear Engineering and Design. 389:111666
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1ac26e93b72c7b2606e259ce49fb52be
https://doi.org/10.1016/j.nucengdes.2022.111666
https://doi.org/10.1016/j.nucengdes.2022.111666
Autor:
Kirill S. Dolganov, Evgeny A. Dolzhenkov, Alexey L. Fokin, Arkady E. Kiselev, Dmitry Yu Tomashchik, Vladimir N. Semenov
Publikováno v:
Annals of Nuclear Energy. 167:108858
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9606813714ae8533ec8932f5061ed0fb
https://doi.org/10.1016/j.anucene.2021.108858
https://doi.org/10.1016/j.anucene.2021.108858
Publikováno v:
Nuclear Engineering and Design. 369:110852
The paper discusses the results of numerical assessment of LWR fuel bundle degradation phenomena during heating up in a flowing steam and top flooding with water under severe accident conditions that were investigated in the PARAMETER-SF1 test. The s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5e21369c6da9dd10e4a36bbfd14a5628
https://doi.org/10.1016/j.nucengdes.2020.110852
https://doi.org/10.1016/j.nucengdes.2020.110852
Autor:
Nikolay V. Bukin, Valery V. Astakhov, Dmitry Yu. Tomashchik, Stanislav I. Pantyushin, Alexey L. Fokin, K. S. Dolganov, Arkady Ye. Kiselev, Dmitry L. Gasparov, V. N. Semenov, Anna V. Nikolaeva, Mikhail A. Bykov
Publikováno v:
Nuclear Engineering and Design. 353:110222
This paper presents the results of calculations of the loadings that reactor main joint may experience after energetic fuel-coolant interaction in a hypothetical severe accident at VVER-1200 reactor. Estimates of the loadings are performed using a se
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b3aff95cea71966eaa9fca76da328833
https://doi.org/10.1016/j.nucengdes.2019.110222
https://doi.org/10.1016/j.nucengdes.2019.110222