. . . . . "RIV/46356088:_____/05:4!RIV06-MPO-46356088" . "V\u00FDvoj nov\u00E9 metodiky pro \u0159e\u0161en\u00ED bezpe\u010Dnosti JE p\u0159i hav\u00E1rii \u00FAnik na sekund\u00E1rn\u00ED stran\u011B."@cs . "V\u00FDvoj nov\u00E9 metodiky pro \u0159e\u0161en\u00ED bezpe\u010Dnosti JE p\u0159i hav\u00E1rii \u00FAnik na sekund\u00E1rn\u00ED stran\u011B." . . "Safety analysis, Safety analysis report, thermal hydraulic analysis, 3D neutron kinetics, main steam line break, best estimete methodology, uncertanties, critical heat flux, safety limits"@en . "05:MPO2T03" . "V\u00FDvoj nov\u00E9 metodiky pro \u0159e\u0161en\u00ED bezpe\u010Dnosti JE p\u0159i hav\u00E1rii \u00FAnik na sekund\u00E1rn\u00ED stran\u011B." . "Prodlou\u017Een\u00ED provozn\u00ED \u017Eivotnosti JE Dukovany o 10 a\u017E 20 let. To bude podm\u00EDn\u011Bno tak\u00E9 d\u016Fsledn\u00FDm zaji\u0161t\u011Bn\u00EDm zvl\u00E1dnut\u00ED hypotetick\u00FDch t\u011B\u017Ek\u00FDch hav\u00E1ri\u00ED dle p\u0159\u00EDstup\u016F aplikovan\u00FDch v EU." . . . . . "550796" . . . "V\u00FDvoj nov\u00E9 metodiky pro \u0159e\u0161en\u00ED bezpe\u010Dnosti JE p\u0159i hav\u00E1rii \u00FAnik na sekund\u00E1rn\u00ED stran\u011B."@cs . . . . . "[A959064310FC]" . . "Nov\u00E1 metodika prov\u00E1d\u011Bn\u00ED bezpe\u010Dnostn\u00EDch v\u00FDpo\u010Dt\u016F typu %22\u00FAnik na sekund\u00E1rn\u00ED stran\u011B jadern\u00E9ho bloku - v\u00EDcen\u00E1sobn\u00E9 prosknut\u00ED parn\u00EDho potrub\u00ED%22" . "Best Estimate methodology of Main steam line rupture with uncertanties"@en . . "RIV/46356088:_____/05:4" . "P(FD-K2/33)" . "Je vypracov\u00E1n n\u00E1vrh metodiky pro hodnocen\u00ED velk\u00E9ho \u00FAniku chladiva ze strany sekund\u00E1rn\u00EDho okruhu JE VVER 1000/320(Temel\u00EDn) pomoc\u00ED nov\u00E9 metodiky."@cs . "3"^^ . . . . "\u010CEZ, Jadern\u00E1 elektr\u00E1rna Temel\u00EDm a Dukovany" . "Je vypracov\u00E1n n\u00E1vrh metodiky pro hodnocen\u00ED velk\u00E9ho \u00FAniku chladiva ze strany sekund\u00E1rn\u00EDho okruhu JE VVER 1000/320(Temel\u00EDn) pomoc\u00ED nov\u00E9 metodiky." . . "%22Developed methodolgy is posible use for improvement of safety of VVER reactor. The base of developed procedure is next: Uncertainty in prediction of thermal hydraulic system behavior for the purpose of nuclear safety is one among the tools for implementation of more accurate thermal hydraulic analyses in licensing. The uncertainty can be considered for new aspect in safety calculations of behavior of the thermal hydraulic systems of nuclear reactors and in analyses of their safety."@en . "Macek, Ji\u0159\u00ED" . "3"^^ . . . "Best Estimate methodology of Main steam line rupture with uncertanties"@en .