Zobrazeno 1 - 5
of 5
pro vyhledávání: '"T. N. Khokhunova"'
Autor:
E. E. Vorob’ev, M. M. Peregud, T. N. Khokhunova, O. Yu. Mileshkina, S. A. Bekrenev, V. A. Markelov, M. A. Shtremel’
Publikováno v:
Russian Metallurgy (Metally). 2019:1112-1124
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b53aaf17c52682b7897343a0505bdf19
https://doi.org/10.1134/s0036029519100392
https://doi.org/10.1134/s0036029519100392
Publikováno v:
Atomic Energy. 123:235-243
The dependence of dimensional changes occurring in the structural parts made of E-635 zirconium alloy on the metallurgical and operational factors as a result of thermal creep, radiation growth, and radiation creep was studied. Tests close to operati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2cbd9b1fcef44ac9baf637bd2dfe9155
https://doi.org/10.1007/s10512-018-0332-6
https://doi.org/10.1007/s10512-018-0332-6
Autor:
I.A. Evdokimov, T. N. Khokhunova, T.N. Aliev, V. V. Novikov, V. A. Markelov, V. F. Kon’kov, Vladimir V. Likhanskii
Publikováno v:
Atomic Energy. 116:186-193
An engineering model of corrosion of zirconium-niobium alloys is described. It takes account of the alloying composition, the content of lithium and boron in the coolant, the heat flux on the surface of fuel elements and the intensity of the neutron
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a93cb9639911cd98e5ab53803835037
https://doi.org/10.1007/s10512-014-9839-7
https://doi.org/10.1007/s10512-014-9839-7
Autor:
V. N. Shishov, M. M. Peregud, A. V. Nikulina, V. F. Kon'kov, V. V. Novikov, V. A. Markelov, T. N. Khokhunova, G. P. Kobylyansky, A. E. Novoselov, Z. E. Ostrovsky, A. V. Obukhov
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::551eb2936c435b769dadcd3034594031
https://doi.org/10.1520/stp48164s
https://doi.org/10.1520/stp48164s
Autor:
V. N. Shishov, M. M. Peregud, A. V. Nikulina, V. F. Kon’kov, V. V. Novikov, V. A. Markelov, T. N. Khokhunova, G. P. Kobylyansky, A. E. Novoselov, Z. E. Ostrovsky, A. V. Obukhov, M. Limback, B. Kammenzind, S. W. Dean
Publikováno v:
Journal of ASTM International. 5:101127
In the search for more optimal core materials for a water cooled reactor at extended burnup, much attention is paid to alloys of the Zr-Nb and Zr-Nb-Fe-Sn systems. E110 and E635 alloys are two such. In the current VVER fuel cycle, the E110 alloy is u
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33d7340834aaea47126397a45f91195e
https://doi.org/10.1520/jai101127
https://doi.org/10.1520/jai101127