Výsledky vyhledávání

Safety of radioactive waste from two-component nuclear energy system disposed in a deep geological repository for permanent storage: radiological migration equivalence

Autor: A.M. Korelo, E.V. Spirin, A.V. Lopatkin, S.S. Lovachev, V.M. Solomatin, V.K. Ivanov, K.A. Tumanov, E.O. Adamov, S.Yu. Chekin, A.N. Menyajlo

Publikováno v: "Radiation and Risk" Bulletin of the National Radiation and Epidemiological Registry. 29:8-32

The article presents analysis of safety of long-lived high level radioactive waste (RW) disposed for permanent storage in a deep geological repository. According to the study protocol it is necessary to estimate the human and environmental health saf

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::962d9eea8d1534313bcad4af2e55697d
https://doi.org/10.21870/0131-3878-2020-29-4-8-32

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Potential radiological risk for the population during implementation of the Rosatom Proryv project. Part 2. Radiation detriment assessment

Autor: A.V. Proukhin, S.S. Lovachev, V.M. Solomatin, A.A. Kiselev, R.I. Bakin, E.A. Ilichev, A.N. Menyajlo, S.Yu. Chekin, V.K. Ivanov, E.O. Adamov, N.G. Seleva, V.V. Lemekhov

Publikováno v: "Radiation and Risk" Bulletin of the National Radiation and Epidemiological Registry. 29:48-68

Nuclear power is effective and safe source of electricity. Meanwhile, uranium reserves in the earth's crust will run out in 100 years with the development of traditional nuclear reactors. The Rosatom “Proryv” project implementation will allow mul

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::722523beedf11d9716d15ee8cb83eee1
https://doi.org/10.21870/0131-3878-2020-29-4-48-68

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Akademický článek

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Inherently safe pool-type reactor as a generator of low-grade heat for district heating, air conditioning and salt water desalination

Autor: Yu.M. Cherkashov, A.A. Romenkov, E.O. Adamov, V.I. Mikhan, V.I. Semenikhin

Publikováno v: Nuclear Engineering and Design. 173:167-174

The society has a heavy demand for low-grade heat to satisfy its various needs. Different factors govern the expediency of applying nuclear reactors for these purposes. The required capacity of heat sources varies in a very wide range. In a majority

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::657e256ae94fc470169af7dcf4c86888
https://doi.org/10.1016/s0029-5493(97)00104-0

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Status and prospects for pressure-tube water-cooled graphite-moderated reactors

Autor: A. A. Petrov, E. V. Burlakov, Yu. M. Cherkashov, I.I. Grozdov, E.O. Adamov, A. Ya. Kramerov

Publikováno v: Nuclear Engineering and Design. 173:59-66

An overview is given on the 50 year experience in the development of pressure-tube water-cooled graphite-moderated reactors (WCGMR) in Russia and operation of NPPs with RBMK-type reactors. Advantages and shortcomings of WCGMR are pointed out. Also de

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2082312659b302ade3f3ec3eb23147de
https://doi.org/10.1016/s0029-5493(97)00095-2

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Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors

Autor: Yu.S. Strebkov, S.E. Bougaenko, V.B. Ivanov, A.V. Sidorenkov, V.P. Kondratjev, V.M. Chernov, Yu.I. Kazennov, S.N. Votinov, G.A. Birgevoj, V.M. Trojanov, V.A. Kazakov, A.E. Rusanov, I.E. Lyublinski, V.A. Evtikhin, E.O. Adamov, V. Tebus, A. D. Nikulin, M.I. Solonin

Publikováno v: Journal of Nuclear Materials. :370-375

Vanadium-based alloys are most promising as low activation structural materials for DEMO. It was previously established that high priority is to be given to V-alloys of the VTiCr system as structural materials of a tritium breeding blanket and

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::86cc15639a7bee9532290fd14b6d0036
https://doi.org/10.1016/s0022-3115(96)00284-x

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