Reactor safety research in Rossendorf

Citation
Fp. Weiss et al., Reactor safety research in Rossendorf, ATW-INT Z K, 44(6), 1999, pp. 348
Citations number
11
Categorie Soggetti
Nuclear Emgineering
Journal title
ATW-INTERNATIONALE ZEITSCHRIFT FUR KERNENERGIE
ISSN journal
14315254 → ACNP
Volume
44
Issue
6
Year of publication
1999
Database
ISI
SICI code
1431-5254(199906)44:6<348:RSRIR>2.0.ZU;2-9
Abstract
The Institute of Safety Research is one of five scientific institutes of th e "Forschungszentrum Rossendorf c. V." (Rossendorf Research Centre - FZR fo r short). The safety research carried out at Rossendorf is based on many ye ars' experience in the analysis of pressurised water reactors of the Russia n WWER type. WWER reactors still today play a major role in the range of wo rk carried out by the Institute. For example, as part of a programme run by the German Federal Ministry of the Environment, Nature Protection and Reac tor Safety the Institute is assisting the Ukrainian Atomic Energy Authority to establish a modern nuclear power station supervisory regime. The Instit ute now also has similar expertise in safety research for western light wat er reactors, and co-operates with German, European and American research bo dies and with the industry. The key areas of safety research in Rossendorf are in the modelling of ther mohydraulic phenomena in assumed disturbance scenarios, reactor physics and radiation transport, and the response of components and materials. The first section of the research report deals solely with the thermohydrau lic work of the Institute, such as the intermingling processes in the prima ry circuit in relation to boron dilution and cold water transients and mode l development for transient two-phase flows. For its thermohydraulic work t he Institute has constructed a 1:5 model of a German pressurised water reac tor. The experiments are cross-checked with CFD (Computational Fluid Dynami cs) codes.