Zobrazeno 1 - 4
of 4
pro vyhledávání: '"V. S. Zagumennov"'
Autor:
A. G. Volkova, N. I. Rodygina, V. S. Zagumennov, S. G. Kotlyarevskii, Elena V. Zakharova, A. O. Pavlyuk, E. V. Bespala
Publikováno v:
Atomic Energy. 128:24-29
Work has been performed as part of the implementation of measures to reduce the hazard of irradiated graphite during the decommissioning of uranium-graphite nuclear reactors. Electrochemical decontamination is studied as a method of purifying the ind
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::49cf6210979b8314ef75a0488f5bba44
https://doi.org/10.1007/s10512-020-00645-z
https://doi.org/10.1007/s10512-020-00645-z
Publikováno v:
Thermal Engineering. 65:51-56
The problems of accumulation of nuclear fuel spills in the graphite stack in the course of operation of uranium-graphite nuclear reactors are considered. The results of thermodynamic analysis of the processes in the graphite stack at dehydration of a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::223c7268b1d097b8c0fea3f7328d0fd4
https://doi.org/10.1134/s0040601518010056
https://doi.org/10.1134/s0040601518010056
Autor:
S. A. Yakunin, E. V. Bespala, V. S. Zagumennov, A. O. Pavlyuk, S. G. Kotlyarevskii, O. A. Ustinov, V. A. Kashcheev
Publikováno v:
Atomic Energy. 122:252-256
The USG-1 facility was developed to incinerate spent reactor graphite. It is equipped with a monitoring and control system; its maximum capacity is 10 kg/h. Trial combustion of a batch of unirradiated graphite was conducted. The tests showed that the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08bdf597971d01f491d0fb6f98537886
https://doi.org/10.1007/s10512-017-0263-7
https://doi.org/10.1007/s10512-017-0263-7
Autor:
V. V. Lazarchuk, F. A. Dorda, V. A. Matyukha, V. S. Zagumennov, V. V. Tinin, A. K. Ledovskikh, V. G. Balakhonov, E. O. Portnyagina
Publikováno v:
Radiochemistry. 46:475-478
A factorial study is made of precipitation of ammonium polyuranates from nitric acid solutions of uranium in the presence of urea, including measuring the effects of the temperature and urea and uranium concentrations in the initial solution on the s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c5bcf860b7e2393febe180127ddcc31e
https://doi.org/10.1007/s11137-005-0013-x
https://doi.org/10.1007/s11137-005-0013-x