Modeling of Coolant Flow in the Fuel Assembly of the Reactor of a Floating Nuclear Power Plant Using the Logos CFD Program

Author:

Dmitriev S. M.,Dobrov A. A.,Legchanov M. A.,Khrobostov A. E.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering,Condensed Matter Physics

Reference10 articles.

1. S. M. Dmitriev, O. A. Bykh, Yu. K. Panov, N. M. Sorokin, D. L. Zverev, and V. A. Farafonov, Basic Equipment of Nuclear Power Plants with Tank-Type Thermal Neutron Reactors [in Russian], Mashinostroenie, Moscow (2013).

2. S. M. Dmitriev, D. L. Zverev, O. A. Bykh, Yu. K. Panov, and V. A. Farafonov, Basic Equipment of Nuclear Power Plants [in Russian], Vyshéishaya Shkola, Minsk (2015).

3. S. M. Dmitriev, V. E. Luk′yanov, and O. B. Samoilov, Substantiation of a correlation for calculating the critical heat flux in fuel assemblies of an alternative design with stirring intensifier grids for WWER-100, Izv. Vyssh. Uch. Zaved., Yad. Énerg., No. 1, 99–108 (2012).

4. S. M. Dmitriev, A. A. Deulin, A. A. Dobrov, M. A. Legchanov, and A. E. Khrobostov, Application of the LOGOS program to investigation of the distinctive features of hydrodynamics in the fuel assembly of a KLT-40S reactor, Sist. Upravl. Inform. Tekhnolog., 57, No. 3, 232–236 (2014).

5. A. N. Grebennikov et al., Adaptation, Verifi cation, and Use of the LOGOS Software Package for Solution of Problems of Nuclear Power Engineering. Book of Abstracts of the 8th Int. Scientific-Techn. Conference "Ensuring Safety for Nuclear Power Plants with WWERs," Podol′sk (2013), pp. 65–66.

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