Výsledky vyhledávání - "L. A. Kormilitsyna"

Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor

Autor: M. V. Kormilitsyn, L. A. Kormilitsyna, S. B. Pustovalov, A. A. Sedov, S. S. Simonov, S. A. Subbotin, P. A. Fomichenko, T. D. Shchepetina

Publikováno v: Atomic Energy. 132:143-148

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5226f2792b590785f845f416b881c1b5
https://doi.org/10.1007/s10512-023-00917-4

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NFC Russia Infrastructure Readiness Assessment for Development of PSKD-600 Power Reactors

Autor: P. A. Fomichenko, A. A. Sedov, L. A. Kormilitsyna, S. B. Pustovalov, P. N. Alekseev, S. A. Subbotin, M. V. Kormilitsyn

Publikováno v: Atomic Energy. 130:1-5

An implementation assessment of PSKD-600 type power reactors was made. It was established that the readiness level of all PSKD-600 nuclear fuel cycle technologies is no lower than TRL5, and most correspond to readiness level no lower than TRL7, i.e.,

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::981e0e767e946e519a1d82d299e3440d
https://doi.org/10.1007/s10512-021-00764-1

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Molten-Salt Reactor for Nuclear Fuel Cycle Closure on All Actinides

Autor: O. V. Kryukov, L. A. Kormilitsyna, Yu. M. Semchenkov, M. V. Kormilitsyn, A. V. Khaperskaya, Yu. S. Fedorov, O. S. Feinberg, Victor Ignatiev

Publikováno v: Atomic Energy. 125:279-283

It is proposed that a specialized molten-salt reactor facility for burning long-lived actinides be located in direct proximity to a pilot-demonstration center. A full-scale ZhSR-S with thermal power 2400 MW will make it possible to burn all transuran

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::da0a251f7a3e6832c12e34615265a88a
https://doi.org/10.1007/s10512-019-00481-w

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Technical-and-economic analysis and optimization of the full flow charts of processing of radioactive wastes on a polyfunctional plant of pyrochemical processing of the spent nuclear fuel of fast reactors

Autor: V. S. Gupalo, A. G. Osipenko, L. A. Kormilitsyna, V. N. Chistyakov, M. V. Kormilitsyn

Publikováno v: Russian Metallurgy (Metally). 2015:1168-1173

When considering the full flow charts of processing of radioactive wastes (RAW) on a polyfunctional plant of pyrochemical processing of the spent nuclear fuel of NIIAR fast reactors, we corroborate optimum technical solutions for the preparation of R

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::82326e9bd5f223450dc574df906d28e9
https://doi.org/10.1134/s0036029515130078

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