"Since nuclear reactor to experimental model of cooling fuel rod"@en . . . . "L\u00E1vi\u010Dka, David" . "P\u0159\u00EDsp\u011Bvek se zab\u00FDv\u00E1 p\u0159edstaven\u00EDm vybudovan\u00E9ho experiment\u00E1ln\u00EDho za\u0159\u00EDzen\u00ED %22Model chlazen\u00ED palivov\u00E9 ty\u010De v jadern\u00E9m reaktoru%22. Model palivov\u00E9 ty\u010De umo\u017E\u0148uje \u0161ir\u0161\u00EDmu publiku pozorovat jevy z oblasti mechaniky tekutin a termomechaniky. Tyto jevy nelze v\u011Bt\u0161inou spat\u0159it z bezpe\u010Dnostn\u00EDch a z provozn\u00EDch d\u016Fvod\u016F na re\u00E1ln\u00E9m za\u0159\u00EDzen\u00ED. Nezaj\u00EDmav\u011Bj\u0161\u00EDmi a nejd\u016Fle\u017Eit\u011Bj\u0161\u00EDmi jevy je tzv. %22krize varu%22 a s n\u00EDm souvisej\u00EDc\u00ED nestacion\u00E1rn\u00ED p\u0159enos tepla ve v\u00EDcef\u00E1zov\u00E9m proud\u011Bn\u00ED." . . "1"^^ . "Od jadern\u00E9ho reaktoru k experiment\u00E1ln\u00EDmu modelu chlazen\u00ED palivov\u00E9ho proutku" . "P\u0159\u00EDsp\u011Bvek se zab\u00FDv\u00E1 p\u0159edstaven\u00EDm vybudovan\u00E9ho experiment\u00E1ln\u00EDho za\u0159\u00EDzen\u00ED %22Model chlazen\u00ED palivov\u00E9 ty\u010De v jadern\u00E9m reaktoru%22. Model palivov\u00E9 ty\u010De umo\u017E\u0148uje \u0161ir\u0161\u00EDmu publiku pozorovat jevy z oblasti mechaniky tekutin a termomechaniky. Tyto jevy nelze v\u011Bt\u0161inou spat\u0159it z bezpe\u010Dnostn\u00EDch a z provozn\u00EDch d\u016Fvod\u016F na re\u00E1ln\u00E9m za\u0159\u00EDzen\u00ED. Nezaj\u00EDmav\u011Bj\u0161\u00EDmi a nejd\u016Fle\u017Eit\u011Bj\u0161\u00EDmi jevy je tzv. %22krize varu%22 a s n\u00EDm souvisej\u00EDc\u00ED nestacion\u00E1rn\u00ED p\u0159enos tepla ve v\u00EDcef\u00E1zov\u00E9m proud\u011Bn\u00ED."@cs . "Od jadern\u00E9ho reaktoru k experiment\u00E1ln\u00EDmu modelu chlazen\u00ED palivov\u00E9ho proutku"@cs . "Od jadern\u00E9ho reaktoru k experiment\u00E1ln\u00EDmu modelu chlazen\u00ED palivov\u00E9ho proutku" . . . . . "Od jadern\u00E9ho reaktoru k experiment\u00E1ln\u00EDmu modelu chlazen\u00ED palivov\u00E9ho proutku"@cs . "The paper presents the built experimental apparatus %22Model of fuel rod cooling in the nuclear reactor%22. The fuel rod model allows the general public to observe phenomena of fluid mechanics and thermomechanics. Safety and operational reasons usually prevent these phenomena from being observed in real-life equipment. The most interesting and important phenomena are boiling crisis and related nonstationary heat transfer in multi-phase flow."@en . "23640" . "RIV/49777513:23640/10:00504135!RIV11-GA0-23640___" . "276296" . "CFD; PIV. velocity flow field; temperature field; numerical simulation; annular vertical tube"@en . "Since nuclear reactor to experimental model of cooling fuel rod"@en . . . . "1"^^ . . . "[E5320905D2EF]" . . "P(GP101/09/P056)" . . . . "RIV/49777513:23640/10:00504135" .