"Konstruk\u010Dn\u00ED materi\u00E1ly pro modern\u00ED \u0161t\u011Bpn\u00E9 a f\u00FAzn\u00ED jadern\u00E9 reaktory z hlediska jejich odolnosti v\u016F\u010Di degrada\u010Dn\u00EDm proces\u016Fm" . "2014-01-01+01:00"^^ . . . "1"^^ . "RIV/26722445:_____/14:#0000994!RIV15-MSM-26722445" . . "Sborn\u00EDk konference JUVEMATTER 2014, 16.-19.5.2014, z\u00E1mek Ne\u010Dtiny" . "6"^^ . "Konstruk\u010Dn\u00ED materi\u00E1ly pro modern\u00ED \u0161t\u011Bpn\u00E9 a f\u00FAzn\u00ED jadern\u00E9 reaktory z hlediska jejich odolnosti v\u016F\u010Di degrada\u010Dn\u00EDm proces\u016Fm"@cs . . . "Kunzov\u00E1, Kl\u00E1ra" . "2"^^ . . . "construction materials; fusion reactors; fission reactors; materials structure"@en . . "Za provozu jsou konstruk\u010Dn\u00ED \u010D\u00E1sti jadern\u00E9ho reaktoru vystaveny p\u016Fsoben\u00ED cel\u00E9 \u0159ady degrada\u010Dn\u00EDch faktor\u016F. Tento probl\u00E9m je aktu\u00E1ln\u00ED jak u modern\u00EDch \u0161t\u011Bpn\u00FDch reaktor\u016F, tak zejm\u00E9na u f\u00FAzn\u00EDch reaktor\u016F, kdy jsou pou\u017Eit\u00E9 materi\u00E1ly vystaveny synergick\u00FDm \u00FA\u010Dink\u016Fm mechanick\u00E9ho nam\u00E1h\u00E1n\u00ED, agresivn\u00EDho korozn\u00EDho m\u00E9dia, vysok\u00E9 teploty a zna\u010Dn\u00FDm radia\u010Dn\u00EDm tok\u016Fm a d\u00E1vk\u00E1m. U pou\u017Eit\u00FDch materi\u00E1l\u016F, kter\u00FDmi jsou nap\u0159. korozivzdorn\u00E9 oceli r\u016Fzn\u00FDch typ\u016F, Ni-slitiny, W-slitiny, V-slitiny, Cu-slitiny, keramick\u00E9 kompozity apod., je proto t\u0159eba sledovat \u0161irok\u00FD okruh vlastnost\u00ED - od chemick\u00E9ho slo\u017Een\u00ED, mikrostruktury, statick\u00FDch mechanick\u00FDch charakteristik, tepeln\u00E9 vodivosti a\u017E po odolnost v\u016F\u010Di vysok\u00FDm teplot\u00E1m, agresivn\u00EDm m\u00E9di\u00EDm a radia\u010Dn\u00EDmu z\u00E1\u0159en\u00ED. P\u0159i n\u00E1vrhu a dimenzov\u00E1n\u00ED cel\u00E9 \u0159ady konstruk\u010Dn\u00EDch \u010D\u00E1st\u00ED jadern\u00FDch reaktor\u016F se pou\u017E\u00EDv\u00E1 konstruk\u010Dn\u00ED filosofie typu \u201Edamage tolerance\u201C. Vzhledem k vysok\u00FDm n\u00E1rok\u016Fm kladen\u00FDm na bezpe\u010Dnost, spolehlivost a \u017Eivotnost je proto nezbytn\u00E9 br\u00E1t v \u00FAvahu i lomov\u011B mechanick\u00E9 charakteristiky pou\u017Eit\u00FDch materi\u00E1l\u016F, kvantifikuj\u00EDc\u00ED nap\u0159. jejich odolnost v\u016F\u010Di stabiln\u00EDmu i nestabiln\u00EDmu \u0161\u00ED\u0159en\u00ED trhlin apod. P\u0159i experiment\u00E1ln\u00EDm ov\u011B\u0159ov\u00E1n\u00ED po\u017Eadovan\u00FDch vlastnost\u00ED je t\u0159eba v\u011Bnovat pozornost nejen v\u011Brohodnosti a reprodukovatelnosti z\u00EDskan\u00FDch dat, ale i ekonomick\u00E9 str\u00E1nce."@cs . "Construction materials for advanced nuclear fission and fusion reactors in terms of their resistance to degradation processes"@en . . . "Za provozu jsou konstruk\u010Dn\u00ED \u010D\u00E1sti jadern\u00E9ho reaktoru vystaveny p\u016Fsoben\u00ED cel\u00E9 \u0159ady degrada\u010Dn\u00EDch faktor\u016F. Tento probl\u00E9m je aktu\u00E1ln\u00ED jak u modern\u00EDch \u0161t\u011Bpn\u00FDch reaktor\u016F, tak zejm\u00E9na u f\u00FAzn\u00EDch reaktor\u016F, kdy jsou pou\u017Eit\u00E9 materi\u00E1ly vystaveny synergick\u00FDm \u00FA\u010Dink\u016Fm mechanick\u00E9ho nam\u00E1h\u00E1n\u00ED, agresivn\u00EDho korozn\u00EDho m\u00E9dia, vysok\u00E9 teploty a zna\u010Dn\u00FDm radia\u010Dn\u00EDm tok\u016Fm a d\u00E1vk\u00E1m. U pou\u017Eit\u00FDch materi\u00E1l\u016F, kter\u00FDmi jsou nap\u0159. korozivzdorn\u00E9 oceli r\u016Fzn\u00FDch typ\u016F, Ni-slitiny, W-slitiny, V-slitiny, Cu-slitiny, keramick\u00E9 kompozity apod., je proto t\u0159eba sledovat \u0161irok\u00FD okruh vlastnost\u00ED - od chemick\u00E9ho slo\u017Een\u00ED, mikrostruktury, statick\u00FDch mechanick\u00FDch charakteristik, tepeln\u00E9 vodivosti a\u017E po odolnost v\u016F\u010Di vysok\u00FDm teplot\u00E1m, agresivn\u00EDm m\u00E9di\u00EDm a radia\u010Dn\u00EDmu z\u00E1\u0159en\u00ED. P\u0159i n\u00E1vrhu a dimenzov\u00E1n\u00ED cel\u00E9 \u0159ady konstruk\u010Dn\u00EDch \u010D\u00E1st\u00ED jadern\u00FDch reaktor\u016F se pou\u017E\u00EDv\u00E1 konstruk\u010Dn\u00ED filosofie typu \u201Edamage tolerance\u201C. Vzhledem k vysok\u00FDm n\u00E1rok\u016Fm kladen\u00FDm na bezpe\u010Dnost, spolehlivost a \u017Eivotnost je proto nezbytn\u00E9 br\u00E1t v \u00FAvahu i lomov\u011B mechanick\u00E9 charakteristiky pou\u017Eit\u00FDch materi\u00E1l\u016F, kvantifikuj\u00EDc\u00ED nap\u0159. jejich odolnost v\u016F\u010Di stabiln\u00EDmu i nestabiln\u00EDmu \u0161\u00ED\u0159en\u00ED trhlin apod. P\u0159i experiment\u00E1ln\u00EDm ov\u011B\u0159ov\u00E1n\u00ED po\u017Eadovan\u00FDch vlastnost\u00ED je t\u0159eba v\u011Bnovat pozornost nejen v\u011Brohodnosti a reprodukovatelnosti z\u00EDskan\u00FDch dat, ale i ekonomick\u00E9 str\u00E1nce." . . "P(ED2.1.00/03.0108)" . "In operation, reactor components exposed to a wide range of degrading factors. This problem is current in modern fission reactors, in particular for the fusion reactor, where the materials are exposed to the synergistic effects of mechanical stress, corrosion of aggressive media and high temperatures and significant radiation doses and flows. For the materials, which are e.g. different types of stainless steel, Ni-alloy, W-alloy, V-alloy, Cu-alloys, ceramic composites, etc., it is therefore necessary to monitor a wide range of properties - the chemical composition, microstructure, mechanical static characteristics, thermal conductivity to resistance to high temperatures, aggressive media and radiation rays. The design and dimensioning of a number of components of nuclear reactors used design philosophy of %22damage tolerance%22. Due to the high demands placed on safety, reliability and durability is therefore necessary to take into account the fracture mechanical characteristics of the materials, quantifying such. Their resistance to the stable and unstable crack propagation, etc. In an experimental verification of the required properties need to pay attention not only to the credibility and reproducibility obtained data, but also in economic terms."@en . . "Ne\u010Dtiny" . "[E6AE87C93EE3]" . "Konstruk\u010Dn\u00ED materi\u00E1ly pro modern\u00ED \u0161t\u011Bpn\u00E9 a f\u00FAzn\u00ED jadern\u00E9 reaktory z hlediska jejich odolnosti v\u016F\u010Di degrada\u010Dn\u00EDm proces\u016Fm" . "\u010Cesk\u00E9 vysok\u00E9 u\u010Den\u00ED technick\u00E9 v Praze" . "978-80-01-05546-5" . . . . "Construction materials for advanced nuclear fission and fusion reactors in terms of their resistance to degradation processes"@en . "Konstruk\u010Dn\u00ED materi\u00E1ly pro modern\u00ED \u0161t\u011Bpn\u00E9 a f\u00FAzn\u00ED jadern\u00E9 reaktory z hlediska jejich odolnosti v\u016F\u010Di degrada\u010Dn\u00EDm proces\u016Fm"@cs . . "24887" . "Praha" . . "RIV/26722445:_____/14:#0000994" .