Johannes Fachinger

TL;DR: In this paper, the authors focus on understanding and modelling the barrier performance of an HTR fuel element with respect to their barrier function, and on the development of an overall model for performance assessment.

TL;DR: In this article, the authors proposed a method for decontaminating graphite from radionuclides using steam reforming, which is an alternative to pure thermal treatment in an inert atmosphere, as was first demonstrated in the HTR-N/N1 project.

TL;DR: Corrosion experiments with non-irradiated uranium-aluminium fuel elements were performed in MgCl 2 -rich brine as discussed by the authors, and it was shown that about 90% of the initially available metallic U and Al precipitated.

TL;DR: In this article, the authors describe the fabrication process of high temperature reactor (HTR) fuel elements in terms of their inherent safety features and the alternative possibilities of applications, e.g. in the production of liquid hydrocarbons or the alternative application in H 2 generation.

TL;DR: In this article, a graphite composite material with an inorganic binder has been developed with a density > 99.7% of theoretical density and a negligible porosity, which represents a long term stable leaching resistant matrix applicable for the embedding of irradiated graphite (i-graphite).