Dissertation / PhD Thesis/Book PreJuSER-43983

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Wärmetechnische Untersuchung eines Transmutationssystems mit flüssigem Brennstoff



2004
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Jülich : Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag, Berichte des Forschungszentrums Jülich 4133, IV, 134 S. () = Aachen, Techn. Hochsch., Diss., 2004

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Report No.: Juel-4133

Abstract: The only way to get a guaranteed supply and technically feasible solution to obtain electric energy without producing Carbondioxide is the fission of heavy nuclides. But the radiotoxicity of the remaining nuclear waste has to be minimized using techniques that are available today. Today's nuclear waste disposal strategy requires a safe enclosure for a time period of at least 1 million years. It is questionable, how far any influences on the safety of the waste enclosure strategy can be prognosed for this time period. Another way to deal with the remaining waste is to transmute the long-lived nuclides into nuclides with a shorter half-life. Additional electric energy can be produced. Therefore, starting from todays strategies, different ways to deal with nuclear waste are discussed. The different possibilities show that there is the need for a suitable system to transmute the nuclear waste in any case. Main focus of this thesis is the technical analysis of a system designed to transmute nuclear waste. To show which measures are necessary to ensure the technically safe operation of such a system, one possible system concept is presented. Through a detailed consideration of the single system components, highly loaded parts are identified, their load is shown and possible improvements for load reduction are presented. In this context especially the choice of a suitable cooling liquid (Pb or Pb/Bi) and the related corrosion processes are discussed. Moreover following these investigations it becomes obvious, that the liquid fuel to be used here (solved in Pb/Bi) requires the application of suitable fuel elements. For these fuel elements it is investigated, whether the materials to be used can stand the loads for a sufficiently long period of time. The analyses focus on the thermal loads on the fuel elements. Due to the liquid state of the fuel the developing natural convection flow has to be considered. This flow influences the resulting loads significantly and is the main part of the further investigations. Based on these results the actual loads are computed and simultaneously the most important influences on the thermal load of the structural materials are shown. These investigations are fundamental for further possible improvements of the system and their corresponding efficiency proposed in the last part of the work presented.


Note: Record converted from VDB: 12.11.2012
Note: Aachen, Techn. Hochsch., Diss., 2004

Contributing Institute(s):
  1. Institut für Sicherheitsforschung und Reaktortechnik (ISR)
Research Program(s):
  1. Nukleare Sicherheitsforschung (E04)

Appears in the scientific report 2004
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 Record created 2012-11-13, last modified 2024-07-12


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