. "Increasing utilization of nuclear fuel through optimization of an inner fuel cycle and calculation of neutron-physics characteristics of nuclear reactor cores"@en . "nuclear fuel reload patterns optimization" . "C\u00EDlem projektu je vytvo\u0159en\u00ED softwarov\u00E9ho produktu pro v\u00EDcecyklovou optimalizaci vs\u00E1zek jadern\u00E9ho paliva v jadern\u00FDch elektr\u00E1rn\u00E1ch. Budou vytvo\u0159eny r\u016Fzn\u00E9 verze modul\u016F pro v\u00FDpo\u010Det neutronov\u011B-fyzik\u00E1ln\u00EDch charakteristik aktivn\u00EDch z\u00F3n jadern\u00FDch reaktor\u016F. Rovn\u011B\u017E bude vytvo\u0159en modul pro stanoven\u00ED termohydraulick\u00FDch charakteristik aktivn\u00EDch z\u00F3n jadern\u00FDch reaktor\u016F. Pro v\u0161echny vyvinut\u00E9 v\u00FDpo\u010Dtov\u00E9 metody bude tak\u00E9 c\u00EDlem jejich efektivn\u00ED paraleln\u00ED implementace na symetrick\u00E9 multiprocesorov\u00E9 syst\u00E9my. V p\u0159\u00EDpad\u011B modul\u016F implementuj\u00EDc\u00EDch nod\u00E1ln\u00ED p\u0159\u00EDstupy budou vyvinuty paraleln\u00ED algoritmy pro pou\u017Eit\u00ED na grafick\u00FDch akceler\u00E1torech. Pro jednotliv\u00E9 moduly budou provedeny srovn\u00E1vac\u00ED v\u00FDpo\u010Dty se standardn\u00EDmi benchmarky a srovn\u00E1n\u00ED s p\u0159esn\u011B definovan\u00FDmi experimenty na jadern\u00E9m reaktoru VR-1. Na z\u00E1v\u011Br projektu prob\u011Bhne legislativn\u00ED standardizace softwarov\u00E9ho produktu podle vyhl\u00E1\u0161ek St\u00E1tn\u00EDho \u00FA\u0159adu pro jadernou bezpe\u010Dnost." . "2015-05-05+02:00"^^ . "TA01020352" . . " CUDA" . . . . "2014-12-31+01:00"^^ . "0"^^ . "2013-05-28+02:00"^^ . . " neutron transport" . . "1"^^ . " computer code quality assurance" . "nuclear fuel reload patterns optimization; neutron transport; neutron diffusion; core thermal-hydraulics characteristics; CUDA; computer code verification and validation; computer code quality assurance; training nuclear reactor VR-1"@en . "1"^^ . . . " computer code verification and validation" . . . "http://www.isvav.cz/projectDetail.do?rowId=TA01020352"^^ . " core thermal-hydraulics characteristics" . . . "25"^^ . "The project focuses primarily on development of a complex software system designed for nuclear fuel reload optimization together with calculations of neutron-physics characteristics of a reactor core. The software is intended to work for different reactor core geometries (mainly the two mostly used, hexagonal and rectangular). It will allow to perform one cycle optimization as well as multicycle optimization of nuclear fuel reload pattern for specified cycle lengths (also e.g. for the equilibrium state). From the point of view of reactor core physics it will enable to calculate a.o. neutron fluxes, burnup, temperature of the fuel during the cycle with very high accuracy. All software optimization and neutron-physics modules will be equipped with a common graphic interface targeted to a standard user. The neutron-physics part of the software system is intended to undergo the verification and validation processes of the State Nuclear Commission of Czech Republic."@en . "25"^^ . . . "Zv\u00FD\u0161en\u00ED vyu\u017Eit\u00ED jadern\u00E9ho paliva pomoc\u00ED optimalizace vnit\u0159n\u00EDho palivov\u00E9ho cyklu a v\u00FDpo\u010Dtu neutronov\u011B-fyzik\u00E1ln\u00EDch charakteristik aktivn\u00EDch z\u00F3n jadern\u00FDch reaktor\u016F" . . . "2011-01-01+01:00"^^ . . . " neutron diffusion" .