001     50675
005     20240712084615.0
024 7 _ |2 Handle
|a 2128/539
024 7 _ |2 URI
|a 539
037 _ _ |a PreJuSER-50675
088 1 _ |a Juel-4188
088 _ _ |a Juel-4188
|2 JUEL
100 1 _ |0 P:(DE-Juel1)VDB59819
|a Barrier, Diane Catherine
|b 0
|e Corresponding author
|u FZJ
245 _ _ |a Characterisation and fabrication of zirconia and thoria based ceramics for nuclear applications
260 _ _ |a Jülich
|b Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
|c 2005
300 _ _ |a 165 p.
336 7 _ |0 PUB:(DE-HGF)11
|2 PUB:(DE-HGF)
|a Dissertation / PhD Thesis
336 7 _ |0 PUB:(DE-HGF)3
|2 PUB:(DE-HGF)
|a Book
336 7 _ |0 2
|2 EndNote
|a Thesis
336 7 _ |2 DRIVER
|a doctoralThesis
336 7 _ |2 BibTeX
|a PHDTHESIS
336 7 _ |2 DataCite
|a Output Types/Dissertation
336 7 _ |2 ORCID
|a DISSERTATION
490 0 _ |0 PERI:(DE-600)2414853-2
|8 23772
|a Berichte des Forschungszentrums Jülich
|v 4188
|x 0944-2952
500 _ _ |a Record converted from VDB: 12.11.2012
502 _ _ |a Aachen, Techn. Hochsch., Diss., 2005
|b Dr. (FH)
|c Techn. Hochsch. Aachen
|d 2005
520 _ _ |a The reduction of the long term radiotoxicity of nuclear waste during disposal is the aim of the research called “Partitioning & Transmutation of minor actinides (MAs)”, which also requires the development of inert ceramic support materials. Moreover, after separation, if the transmutation is not available, the actinides can be conditioned into stable dedicated solid matrices (Partitioning & Conditioning strategy). Yttrium-stabilized zirconia and thoria are discussed in the international nuclear community as candidates for the fixation of long-lived actinides as target material for transmutation and as stable materials for long-term final disposal. The aims of the following work are twofold: determine the impact of the addition of actinides, simulated by cerium on the properties of the matrices and study the possibility of synthesising homogeneous ceramics using simple fabrication routes. Within this framework, (Zr,Y)O$_{2-x}$ - CeO$_{2}$ and ThO$_{2}$ - CeO$_{2}$ powders with variable ceria contents (from 0 to 100 %) were synthesised by a co-precipitation method of nitrate solution. The influence of ceria concentration on the powder' properties, such as thermal behaviour and the evolution of material crystallisation during annealing, was investigated in detail by thermogravimetry (TG) coupled with differential scanning calorimetry (DSC) and X-ray diffraction (XRD). Both systems crystallise at high temperature in a stable solid solution, fcc, fluorite type structure and follow the Vegard’s law for the complete range of ceria. For both systems a critical concentration of 20 mol % has been established. For ceria concentrations lower than 20 %, the properties of the system are mainly controlled by the matrix. Pellets with different ceria concentrations were compacted from these powders by using different technological cycles. In order to obtain materials with reliable properties, the technological parameters of each chosen fabrication route, have been optimised. By employing mild wet methods (calcination at 600°C, wet-grinding in acetone and fractionation in acetone), (Zr,Y,Ce)O$_{2-x}$ pellets with densities of up to 0.97 TD can be obtained. In the case of the (Th,Ce)O$_{2}$ system, pressing by repressing from non-milled powder was selected as the fabrication route, allowing the fabrication of pellets with densities of up to 0.98 TD. In both cases, materials with homogeneous repartition of pores, well formed grains and boundaries and good mechanical properties were obtained.
536 _ _ |0 G:(DE-Juel1)FUEK249
|2 G:(DE-HGF)
|a Nukleare Sicherheitsforschung
|c E04
|x 0
655 _ 7 |a Hochschulschrift
|x Dissertation (FH)
856 4 _ |u https://juser.fz-juelich.de/record/50675/files/Juel_4188_Barrie.pdf
|y OpenAccess
909 C O |o oai:juser.fz-juelich.de:50675
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913 1 _ |0 G:(DE-Juel1)FUEK249
|b Energie
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|l Nukleare Sicherheitsforschung
|v Nukleare Sicherheitsforschung
|x 0
914 1 _ |a Nachtrag
|y 2005
915 _ _ |0 StatID:(DE-HGF)0510
|2 StatID
|a OpenAccess
920 1 _ |0 I:(DE-Juel1)VDB182
|d 31.12.2006
|g ISR
|k ISR
|l Institut für Sicherheitsforschung und Reaktortechnik
|x 0
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