"2"^^ . "Plze\u0148" . "Vliv pru\u017En\u011B-visk\u00F3zn\u00EDch tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny"@cs . "0"^^ . "Plze\u0148" . "Influence of the visco-elastic dampers on modal properties of the nuclear power plant primary circuit"@en . "2"^^ . "0"^^ . . "Nuclear power plant primary circuit; modal properties; visco-elastic dampers"@en . "Vliv pru\u017En\u011B-visk\u00F3zn\u00EDch tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny"@cs . . "Vliv pru\u017En\u011B-visk\u00F3zn\u00EDch tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny" . "Hlav\u00E1\u010D, Zden\u011Bk" . . . . "Vliv pru\u017En\u011B-visk\u00F3zn\u00EDch tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny" . "700700" . . "V\u00FDpo\u010Dtov\u00FD model prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny zahrnuje reaktor a chladic\u00ED smy\u010Dky s hlavn\u00EDmi komponentami a tlumi\u010Di. Matice tlumen\u00ED syst\u00E9mu s visko-elastick\u00FDmi tlumi\u010Di nen\u00ED proporcion\u00E1ln\u00ED a spolu s matic\u00ED tuhosti je frekven\u010Dn\u011B z\u00E1visl\u00E1. Pro modelov\u00E1n\u00ED a mod\u00E1ln\u00ED anal\u00FDzu je vyu\u017Eita metoda mod\u00E1ln\u00ED syst\u00E9zy s redukc\u00ED po\u010Dtu stup\u0148\u016F volnosti. Analyzov\u00E1n je vliv tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti." . . . . "Influence of the visco-elastic dampers on modal properties of the nuclear power plant primary circuit"@en . . . . "RIV/49777513:23520/01:00063820!RIV/2002/GA0/235202/N" . . "80-7082-780-7" . . "Z\u00E1pado\u010Desk\u00E1 univerzita v Plzni" . . "2001-01-01+01:00"^^ . "Vliv pru\u017En\u011B-visk\u00F3zn\u00EDch tlumi\u010D\u016F na mod\u00E1ln\u00ED vlastnosti prim\u00E1rn\u00EDho okruhu jadern\u00E9 elektr\u00E1rny" . "The nuclear power plant primary circuit includes the reactor and the primary coolant loops with all main components (steam generators, main circulating pumps). The damping matrix of the system with visco-elastic dampers is not proportional and like the stiffness matrix is frequency dependent. For modelling and modal analysis the modal synthesis method with DOF reduction is applied. The method is used for the modal analysis of the nuclear power plant with Russian type of WWER 440 reactor with six coolant loops and visco-elastic dampers GERB."@en . . "S. 453-460" . "Zeman, Vladim\u00EDr" . . "P(GA101/00/0345)" . "23520" . "[97DBB8419F50]" . "8"^^ . "RIV/49777513:23520/01:00063820" .