Strontium-89- und Strontium-90-Bestimmungen bei der Entwicklung Graphitmoderierter Hochtemperaturreaktoren

A summary is given about hitherto studied and applied versions of sample pretreatment and separation techniques of⁸⁹Sr and⁹⁰Sr from fission and activation products in plate-out experiments for security studies of graphite moderated gas cooled high temperature pebble bed reactors. The latest and most succesfully applied version with a combined double-column system is described and its performance and results are discussed in detail.