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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
1

Parní kotel s přihříváním páry na spalování vysokopecního plynu / Boiler with steam reheating for burning blast furnace gas

Šenovský, Petr January 2014 (has links)
The aim of this Diploma thesis is design of steam boiler with steam reheating, for combustion the blast furnace gas. The fuel composition and primary parameters for calculation of the boiler were provided. In the first part the fuel composition is described. The main part of the thesis consists of stoichiometric calculations, establishing efficiency of the boiler, calculating combustion chamber as well as design and calculation individual heating surfaces. Part of the work is also drawing documentation of boiler.
2

Systémy přeměn energie pro jaderné elektrárny se sodíkem chlazeným reaktorem (SFR) / Energy conversion systems for nuclear power plants with soduim fast reactor (SFR)

Netopilová, Petra January 2011 (has links)
The aim of the dissertation is proposing and solving energy convection systems for nuc-lear power plants with a sodium fast reactor of the 4th generation. The first part of the dissertation deals with collection and evaluation of information available about nuclear power plants with sodium fast reactor which use nuclear or non-nuclear reheating to increase thermal efficiency. On the basis of the acquired information, thermal schemes are developed and thermal effi-ciency is determined for the systems working in both Rankine thermal cycle and Brayton thermal cycle. In the further part of the dissertation thermal calculation of the reheater for nuclear and non-nuclear reheating is made for the systems working in Rankine thermal cycle. At the end of this dissertation, an apparatus suitable for these systems is suggested and the systems are evaluated in terms of technical implementation and nuclear safety.

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