Zobrazeno 1 - 10
of 34
pro vyhledávání: '"O. A. Ustinov"'
Autor:
O. A. Ustinov, S. A. Yakunin
Publikováno v:
Radiochemistry. 63:395-400
With regard to the radioactive waste vitrification technology, literature data on the behavior of technetium and its release into the gas phase are reviewed. In various types of spent nuclear fuel (SNF), the content of technetium varies from 16 to 13
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb07112983863e51b744aa349676c898
https://doi.org/10.1134/s1066362221040019
https://doi.org/10.1134/s1066362221040019
Publikováno v:
Radiochemistry. 63:263-268
As applied to the radioactive waste vitrification technology, it was established that ruthenium exists in nitric acid solutions in the form of nitrate complexes, which decompose on heating with the release of volatile RuO4 at a nitric acid concentrat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d22b598e5f264285cebd978e38051839
https://doi.org/10.1134/s1066362221030024
https://doi.org/10.1134/s1066362221030024
Publikováno v:
Atomic Energy. 127:99-104
Dinitrogen oxide N2O (nitrogen hemioxide) is one of the harmful components of the off-gases during the reprocessing of spent nitride fuel. It enters the gas phase during the dissolution of nitride fuel in nitric acid and denitration of high-activity
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9dc7b2720575a968c6822624873ae02
https://doi.org/10.1007/s10512-019-00592-4
https://doi.org/10.1007/s10512-019-00592-4
Publikováno v:
Atomic Energy. 127:105-108
A variant of a gas cleanup system for the vitrification of liquid radwaste is proposed. The characteristics of the gas flow formed upon inclusion of liquid high-level waste in borosilicate glass are examined. Two approaches to a gas cleanup system fo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::03967dd0801ff8c8ce297841d0480b14
https://doi.org/10.1007/s10512-019-00593-3
https://doi.org/10.1007/s10512-019-00593-3
Autor:
A. A. Semenov, O. A. Ustinov, A. Yu. Shadrin, A. I. Tuchkova, I. G. Lesina, A. S. Anikin, V. A. Kashcheev
Publikováno v:
Atomic Energy. 125:244-249
The formation of tritium in reactors, its behavior in nitride fuel and possibility of bonding with fission products, and the characteristics of migration out of the fuel-element cladding are examined. It is shown by a computational method that owing
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a729c71c97b91617b55b6ce6196050bf
https://doi.org/10.1007/s10512-019-00474-9
https://doi.org/10.1007/s10512-019-00474-9
Autor:
A. A. Cherepanov, O. A. Ustinov, S. A. Yakunin, L. V. Litvinyuk, S. I. Nelyubin, I. V. Zarubin, M. V. Batashov
Publikováno v:
Theoretical Foundations of Chemical Engineering. 52:760-764
A low-concentration nitrogen oxide recovery unit with a capacity of 50 m3/h equipped with γ-Al2O3 granules saturated with a water solution of carbamide and ammonium bicarbonate has been developed, produced, and tested. During the tests, the unit ope
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::85aeb1799e8736602ac0ae307f99ce7d
https://doi.org/10.1134/s0040579518040036
https://doi.org/10.1134/s0040579518040036
Publikováno v:
Atomic Energy. 124:105-110
A gas-purification system with maximum capacity 50 m3/h was developed, fabricated, and tested to catch nitrogen oxides released during hydrometallurgical processing of spent fuel from the BREST reactor. To catch nitrogen oxides, the setup employs wat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd89bd6b6fe939fbe6b393ee2f01ebe2
https://doi.org/10.1007/s10512-018-0382-9
https://doi.org/10.1007/s10512-018-0382-9
Publikováno v:
Atomic Energy. 123:244-247
A local gas-purification system of the voloxidation operation is examined within the framework of the technology of regeneration of spent mixed uranium-plutonium nitride fuel from fast reactors. The system includes a metal-fabric filter, HEPA filter,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34cf3d6ce8d6865baf548111ec2767fe
https://doi.org/10.1007/s10512-018-0333-5
https://doi.org/10.1007/s10512-018-0333-5
Publikováno v:
Atomic Energy. 123:59-62
14C enters the atmosphere in amounts equivalent to 1.4 PBq/yr with total accumulation 140 PBq via cosmic radiation. As a result of nuclear explosions (1950–1969), its activity in the atmosphere exceeded 200 PBq. At present, 14C has been completely
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f2b893c70110b49a498c34410b9e79c
https://doi.org/10.1007/s10512-017-0301-5
https://doi.org/10.1007/s10512-017-0301-5
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