Graphitic Matrix Materials for Spherical HTR Fuel Elements : Results of Material Development and Irradiation Testing : Catalogue of Pictures and Tables

Abstract

The present report comprises the essential results of material development and irradiation testing of graphitic matrix materials for spherical HTR fuel elements and completes the documentation of the irradiation data for 20 matrix materials (Jül-1702). The main emphasis is given to the matrices A3-3 (standard matrix) and A3-27 (matrix with synthesized resin), both of which are being used as structural materials for the fuel elements of the AVR and THTR reactors*.) In addition, comparisons are made between 18 A3-variants and the standard matrix A3-3, which show that three of the variants may be considered as a further potential for use. Moreover, the possibilities for HTR fuel elements which are opened up by the introduction of a new technology, warm moulding, are also illustrated. The results described were obtained within the framework of the HTR project "Hochtemperaturreaktor-Brennstoffkreislauf" (High-Temperature Reactor Fuel Cycle) involving the Gesellschaft für Hochtemperaturreaktor-Technik mbH, Hochtemperaturreaktor-Brennelement GmbH, Hochtemperatur-Reaktorbau GmbH, Kernforschungsanlage Jülich GmbH, NUKEM GmbH and Sigri Elektrographit GmbH/ Ringsdorff-Werke GmbH. The project is sponsored by the "Bundesministerium für Forschung und Technologie" (Federal Ministry for Research and Technology) and by the State of North-Rhine/Westphalia