caa a22 4500 606151427 CHVBK 20210128100543.0 cr unu---uuuuu 210128e20150201xx s 000 0 eng 10.1007/s10512-015-9915-7 doi (NATIONALLICENCE)springer-10.1007/s10512-015-9915-7 PUChOK BM-DF Code Verification Based on Experimental Study of the Heat-Exchange Crisis Accompanying Deformation of the Channel Tube of an RBMK Fuel Assembly [Elektronische Daten] [D. Afremov, A. Emel'yanov, A. Kudryavtsev, Yu. Mironov, G. Mingaleeva, V. Radkevich, D. Yashnikov, N. Brus] The model of a heat-exchange crisis used in the PUChOK BM-DF code, intended for calculating by means of elementary cells the local thermohydraulic parameters of water and a steam-water mixture during stationary flow in fuel rod assemblies, was verified. The verification was done on experimental data obtained on the PSB RBMK thermohydraulic stand (Electrogorsk Research Center for Nuclear Power Plant Safety), which models one circuit of the multiple forced circulation loop in RBMK and includes a model of all main elements of the loop. The experimental investigation was performed in order to determine the effect of changes in the geometry of RBMK channels on the conditions for the appearance of a heat-exchange crisis. It was shown that in terms of the local parameters the computed critical power agrees with the experimental data. Springer Science+Business Media New York, 2015 Afremov D. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Emel'yanov A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Kudryavtsev A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Mironov Yu Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Mingaleeva G. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Radkevich V. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Yashnikov D. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut Brus N. Electrogorsk Research Center for Nuclear Power Plant Safety (ENITs), Elektrogorsk, Moscow Oblast, Russia aut Atomic Energy Springer US; http://www.springer-ny.com 117/4(2015-02-01), 231-235 1063-4258 117:4<231 2015 117 10512 https://doi.org/10.1007/s10512-015-9915-7 text/html Onlinezugriff via DOI BK010053 XK010053 XK010000 Metadata rights reserved Springer special CC-BY-NC licence nationallicence 1 research-article jats NATIONALLICENCE NATIONALLICENCE NL-springer NATIONALLICENCE 856 40 https://doi.org/10.1007/s10512-015-9915-7 text/html Onlinezugriff via DOI NATIONALLICENCE 700 1- Afremov D. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Emel'yanov A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Kudryavtsev A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Mironov Yu Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Mingaleeva G. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Radkevich V. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Yashnikov D. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia aut NATIONALLICENCE 700 1- Brus N. Electrogorsk Research Center for Nuclear Power Plant Safety (ENITs), Elektrogorsk, Moscow Oblast, Russia aut NATIONALLICENCE 773 0- Atomic Energy Springer US; http://www.springer-ny.com 117/4(2015-02-01), 231-235 1063-4258 117:4<231 2015 117 10512