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11	Determinacao experimental de indices espectrais por varredura gama de vareta combustivel no reator IPEN/MB-01 / Experimental determination of spectral indices by scanning of fuel rod in the IPEN/MB-01 reactor FANARO, LEDA C.C.B. 09 October 2014 (has links) Made available in DSpace on 2014-10-09T12:26:35Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:06:28Z (GMT). No. of bitstreams: 0 / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP IPEN-MB-1 REACTOR FUEL RODS URANIUM 235 URANIUM DIOXIDE CADMIUM CONFIGURATION CONTROL CRITICALITY UNCERTAINT PRINCIPLE GAMMA SPECTROSCOPY DELAYED NEUTRON FRACTION COMPUTER CODE M CODES T CODES
12	Rozložení výkonu a teplot v palivových souborech reaktoru VVER-440 na Elektrárně Dukovany / Power and Temperature Distribution in Nuclear Fuel Assemblies of VVER-440 reactor at Dukovany NPP Smola, Luděk January 2016 (has links) This Master’s thesis focuses on calculation of power and temperature distribution in fuel assemblies of VVER-440 reactor at Dukovany Nuclear Power Plant. Theoretical section contains a brief description of VVER-440 technology, fuel and its development at Dukovany Nuclear Power Plant, basics of heat generation in nuclear reactors as well as an overview and categorization of computer codes, used for core calculations. Of these codes, the MOBY-DICK computer code is then described in depth, including its input and output files. The MOBY-DICK code is later on used for pinwise calculating power distribution of selected fuel cycles of defined units at Dukovany Nuclear Power Plant, with vizualization of output values for characteristic fuel assemblies. Results of this computation are then used for analysis, whether uneven power distribution in the core and heat generation gradient within fuel assemblies have any influence on measuring channel output temperatures, which is the pivotal part of this thesis.
13	DYN3D version 3.2 - code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements - description of models and methods - Grundmann, Ulrich, Rohde, Ulrich, Mittag, Siegfried, Kliem, Sören 31 March 2010 (has links) (PDF) DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balance equations for mass, energy and momentum of the two-phase mixture and the mass balance for the vapour phase. Various cross section libraries are linked with DYN3D. Systematic code validation is performed by FZR and independent organizations. light water reactors transients computer code core model three-dimensional two group neutron diffusion nodal methods two-phase flow thermal hydraulics fuel rod model reactor safety cross section libraries burnup calculation Xenon and Samarium dynamics coupling system codes
14	DYN3D version 3.2 - code for calculation of transients in light water reactors (LWR) with hexagonal or quadratic fuel elements - description of models and methods - Grundmann, Ulrich, Rohde, Ulrich, Mittag, Siegfried, Kliem, Sören January 2005 (has links) DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balance equations for mass, energy and momentum of the two-phase mixture and the mass balance for the vapour phase. Various cross section libraries are linked with DYN3D. Systematic code validation is performed by FZR and independent organizations.

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