Dr. Frank-Peter Weiss graduated from the Physics Department of the Dresden (Germany) Technical University with a Diploma degree in 1973. He defended his doctoral theses in nuclear reactor physics at the GDR Academy of Sciences in 1986. Since 1973, he has been engaged in different fields of reactor diagnostics and reactor safety at the research campus in Dresden-Rossendorf. Until Oct. 31st, 2010, Dr. Weiss had been Director of the Institute of Safety Research of the research centre Forschungszentrum Dresden-Rossendorf (FZD). In this capacity, he was responsible for the development and coordination of the reactor safety research of the institute. The institute was focussed on (1) accident analysis studies of current and future reactors, (2) development of advanced reactor physics and thermal hydraulic computational tools, (3) development and validation of computational fluid dynamics (CFD) codes for reactor safety applications, and (4) the analysis of irradiation induced ageing effects of reactor pressure vessel steels. Among others, Dr. Weiss has been involved in the topical analysis of boron dilution transients at PWRs and the investigation of loss of coolant accidents at LWRs including sump strainer clogging by released thermal insulation fibres.Since 1994, Dr. Weiss has been Professor at the mechanical engineering faculty of the Dresden Technical University where he lectures on methods for reliability and safety analysis of technical plants.
Since November 1st 2010, F.-P. Weiss has been Scientific-Technical Director of the German Gesellschaft für Anlagen- und Reaktorsicherheit, GRS. F.-P. Weiss is member of the advisory editorial boards of the Annals of Nuclear Energy and the German Journal Kerntechnik. He serves as expert in reactor safety, among others, to the European Commission and the French CEA. He is member of the German Reactor Safety Commission and of INSAG IAEA.