Georg Maier
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Featured researches published by Georg Maier.
Journal of Nuclear Materials | 1979
Wolfgang Dorr; H. Assmann; Georg Maier; J. Steven
Abstract Basically, the quantitative characterization of structural parameters of UO2 pellets is necessary for optimizing their microstructure with respect to in-service performance. Dimensional behaviour (swelling, densification, plasticity) as well as fission gas and fission product release are dependent on density, open porosity, pore size distribution and specific surface area of the pellets. Measurement techniques for one or several of these properties are reported together with typical results on UO2 pellets from the AUC conversion process.
Journal of Nuclear Materials | 1988
Georg Maier; H. Assmann; Wolfgang Dorr
Abstract There are two ways to predict dimensional behaviour during irradiation: 1. (i) quantitative analysis of the density and pore structure and model calculation, and 2. (ii) thermal resinter testing and application of a predicting correlation between measured density changes and in-pile densification. This paper gives a comparison between predicted in-pile densification and actual densification as determined by post-irradiation examination. A mechanistic model for thermal and fission-induced densification was applied. It was shown that the model predictions and the experimental results agreed well. Thus it was possible to derive a relation for the out-pile simulation of in-reactor behaviour which is applicable in quality control practice. However, long resintering periods are necessary for the simulation of high burnup.
Journal of Nuclear Materials | 1982
Martin Peehs; Wolfgang Dorr; Gerhard Gradel; Georg Maier
The thermal diffusivity and the thermal conductivity were measured for UO2-Gd2O3 with Gd2O3 ⩽ 10 W/O in the temperature range 25 °C ⩽ ⩽ 500 °C. An evaluation of the experimental data has shown, that the thermal conductivity is mainly influenced by microstructural changes in the mixed oxide structure due to Gd2O3-content. This result was also confirmed by detailed investigations of the structure of UO2-Gd2O3. Measurements of the stationary creep rate at Δ = 1500 °C and 100 N/mm2 from UO2 and UO2-6,5 W/O Gd2O3, showed, that the plasticity of such fuel is scarcely influenced by the Gd2O3, content.
Journal of Nuclear Materials | 1982
Wolfgang Dorr; Georg Maier; Martin Peehs
Zusammenfassung LWR fuel for high-burn up has initiated some efforts at the accommodation of the microstructural fuel properties. The adaption of the pore size can easily be performed by the addition of U 3 O 8 in well defined powder fractions. The adjustment of a coarse grain structure without the addition of oxidic dopants can be reached by using an oxidative sintering process. This process utilizes the diffusion enhancing effect of interstitial oxygen in UO 2 . Both measures do not only guarantee a reliable adjustment of the fuel properties, but also meet the conditions for a well controlled manufacturing procedure.
Journal of Nuclear Materials | 1981
H. Assmann; Wolfgang Dorr; Gerhard Gradel; Georg Maier; Martin Peehs
Archive | 1985
Georg Maier
Archive | 1981
Georg Maier
Archive | 1982
Helmut Assmann; Gerhard Dichtjar; Wolfgang Dorr; Georg Maier; Viktor Mathieu; Martin Peehs
Archive | 1984
Helmut Assmann; Georg Maier; Wolfgang Dorr; Martin Peehs
Archive | 1989
Martin Peehs; Heinrich Bayer; Ulrich Jenczio; Jurgen Laucht; Sieghard Hellmann; Gerhard Dichtjar; Wolfgang Dorr; Georg Maier