Výsledky vyhledávání - "V. A. Kuprienko"

Influence of Y and Zr on TiAl43Nb4Mo1B0.1 titanium aluminide microstructure and properties

Autor: A. V. Fadeev, A. I. Bazlov, V. D. Belov, I. A. Logachev, V. E. Bazhenov, A. Yu. Titov, I. V. Plisetskaya, V. S. Kuprienko, A. A. Komissarov, A. V. Koltygin

Publikováno v: Materials Science and Technology. 36:548-555

The influence of the addition of 2.3 at.-% Y and of 0.8 at.-% Zr + 0.2 at.-% Y on the properties of TiAl43Nb4Mo1B0.1 (TNM-B1) titanium aluminide alloy is investigated. Energy-dispersive X-ray spect...

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::11f9ce00f3f05d8ef4e526c69eef9c6e
https://doi.org/10.1080/02670836.2020.1716493

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Controlled neutron field system at NIIAR reactors

Autor: V. A. Kuprienko, V. P. Yaryna, N. V. Markina, A. A. Boitsov, D. K. Ryazanov, E. I. Grigor'ev, A. V. Klinov

Publikováno v: Measurement Techniques. 38:939-941

The metrological support system for neutron measurements at nuclear reactors has been developed on the concept of controlled neutron fields applicable to organizations having a group of reactors. A metrological classification is proposed for the fiel

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b46140b1a452a5498f951cb8dcdbd7c9
https://doi.org/10.1007/bf00978401

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Experience in Operation of the Experimental Atomic Power Plant 'ARBUS' with the High-Boiling Organic Coolant-Moderator Ditolylmethane

Autor: V. D. Tetyukov, V. A. Tzikanov, Yu. N. Aleksenko, V. A. Khramchenkov, I. G. Kobzar, V. I. Zinoviev, M. P. Mexcheryakov, V. A. Kuprienko

Publikováno v: Nuclear Technology. 38:187-191

Radiolytic damage to the ditolylmethane organic coolant-moderator of the ARBUS reactor was removed by vacuum distillation. The majority of the degraded ditolylmethane formed gaseous and high-boiling materials, which were easily removed by the vacuum

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::1018e141f878eba60ab68b2cdc5928a3
https://doi.org/10.13182/nt78-a32011

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Ritm facility for testing fuel elements in variable power regimes in the SM-2 reactor

Autor: Yu. G. Spiridonov, V. Sh. Sulaberidze, V. A. Kuprienko, A. V. Pershin, V. N. Shulimov

Publikováno v: Soviet Atomic Energy. 58:246-249

This paper addresses the problems originating with a change of the requirements for the operating conditions of nuclear power stations with water-cooled-water-moderated reactors (VVER) in the power generation system. In order to solve the problem of

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c832445c0de37a9dc0c8433bf97d3da5
https://doi.org/10.1007/bf01207210

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