Výsledky vyhledávání - "V.V. Privezentsev"

Akademický článek

Temperature fields and heat transfer in free-packed fuel pin bundles cooled by heavy liquid metal

Autor: A.V. Zhukov, Yu.A. Kuzina, A.P. Sorokin, V.V. Privezentsev

Publikováno v: Nuclear Energy and Technology, Vol 2, Iss 1, Pp 70-75 (2016)

The paper considers heat transfer and temperature fields in a free-packed fuel pin bundle cooled by a heavy liquid metal with different types of spacing. Data is analyzed for three fuel assemblies with a pitch of s/d = 1.33: a smooth fuel pin bundle,

Externí odkaz: https://doaj.org/article/830321f83bc94d16bab3e4758c939f17

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Akademický článek

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

Autor: R.R. Khafizov, V.M. Poplavsky, V.I. Rachkov, A.P. Sorokin, Yu.M. Ashurko, A.V. Volkov, E.F. Ivanov, V.V. Privezentsev

Publikováno v: Nuclear Energy and Technology, Vol 1, Iss 2, Pp 147-152 (2015)

Numerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried out using the COREMELT code indicate the development and spreading of sodium boiling in the core accompanied with fluctuations of reactor technological paramet

Externí odkaz: https://doaj.org/article/91e556cd03044fdf847471de1ed426dd

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Akademický článek

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Akademický článek

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Experimental studies of heat exchange for sodium boiling in the fuel assembly model: Safety substantiation of a promising fast reactor

Autor: E. F. Ivanov, A. P. Sorokin, V. I. Rachkov, A. A. Trufanov, V. M. Poplavskii, R.R. Khafizov, A. V. Volkov, Yu.M. Ashurko, V.V. Privezentsev

Publikováno v: Thermal Engineering. 64:6-14

Numerical simulation of the ULOF-type accident development in a fast reactor with sodium coolant performed using the COREMELT code indicates that sodium boiling in the active core takes place. The boiling is accompanied by oscillations of the technol

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::83aff69d98e7bc4189a770c01ba05edc
https://doi.org/10.1134/s0040601517010037

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Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor

Autor: A. V. Volkov, V. I. Rachkov, Yu. M. Ashurko, E.F. Ivanov, V.V. Privezentsev, R.R. Khafizov, V. M. Poplavskii, A. P. Sorokin

Publikováno v: Atomic Energy. 120:328-334

A structural concept using a sodium cavity located above the core of a reactor is proposed as a means of preventing accidents resulting in the destruction of core elements. The experimental investigations of heat transfer performed on the AR-1 stand

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8e3acd38cf10caa95ff0a0524bba797d
https://doi.org/10.1007/s10512-016-0139-2

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Experimental Investigations of the Characteristics of Heat-Exchange and Temperature Fields in the Channels and Fuel-Element Assemblies of Lead-Cooled Fast Reactors

Autor: Yu. A. Kuzina, V.V. Privezentsev, V. I. Rachkov, A. P. Sorokin, A.V. Zhukov

Publikováno v: Atomic Energy. 118:307-317

The results of experimental investigations of heat exchange and temperature fi elds in channels and fuel assemblies in lead-cooled fast reactors performed at the Leipunskii Institute for Physics and Power Engineering are presented. The main investiga

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::24612a0d051aeef81cc0b7e1dccbef0d
https://doi.org/10.1007/s10512-015-9998-1

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Syngas production by partial oxidation of methane in a microchannel reactor over a Ni–Pt/La0.2Zr0.4Ce0.4Ox catalyst

Autor: A.G. Gribovskii, Valentin N. Parmon, V.V. Privezentsev, Vladislav A. Sadykov, D.V. Andreev, L.L. Makarshin

Publikováno v: Fuel Processing Technology. 131:21-28

Operation of a microchannel reactor during the partial oxidation of methane has been studied. Methods for the deposition of a durable (Ni–Pt)/LaCeZrO catalyst on the Fecralloy microchannel plates working under thermocycling (up to 900 °C) conditio

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4fabf72cc319594f2db1132ea4a36ace
https://doi.org/10.1016/j.fuproc.2014.10.031

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AR-1 experimental model and facility preparation for the purpose of experimental investigation of sodium boiling in fuel subassembly mockup for new generation fast reactor safety justification

Autor: A. V. Volkov, Yu.M. Ashurko, E. F. Ivanov, V.V. Kumskoj, R.R. Khafizov, V.V. Privezentsev, A. P. Sorokin

Publikováno v: Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika. 2014:77-87

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::a34804b3d6aca120d78fb98d6a8b784c
https://doi.org/10.26583/npe.2014.1.05

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Akademický článek

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