Koza, Y. (Forschungszentrum Juelich GmbH...gmbh (germany), forschungszentrum juelic...technische, rheinisch-westfaelische
In zukuenftigen Fusionsreaktoren des Tokamak-Typs werden die an das Plasma grenzenden Materialien unter transienten thermischen Belastungen wie Edge Localized Modes (ELM), Plasma- Disruptionen und vertikalen Plasma-Instabilitaeten (VDE), lokal mit hohen thermische Belastungen beaufschlagt. Unter diesen Bedingungen koennen Rissbildung, thermische Er...
A new experimental approach is introduced to investigate the relaxation of the nuclear deformation degrees of freedom. Highly excited fissioning systems with compact shapes and low angular momenta are produced in peripheral relativistic heavy-ion collisions. Both fission fragments are identified in atomic number. Fission cross sections and fission-...
Schmidt, K.H.Schmitt, C.Jurado, B.Benlliure, J. (Universidad de Santiago d...Gesellschaft fuer Schwerionenforschung m...
We examine the manifestation of transient effects in fission by analysing experimental data where fission is induced by peripheral heavy-ion collisions at relativistic energies. Available total nuclear fission cross sections of "2"3"8U at1.A GeV on gold and uranium targets are compared with a nuclear-reaction code, where transient effects in fissio...
In the event of a hypothetical severe accident in a Light Water Reactor (LWR) it is possible that the core melts and relocates to the lower head of the reactor pressure vessel (RPV). If the severe accident management measures are not successful, the RPV can fail and the core melt is discharged onto the basement of the containment. To prevent a sign...
The Forschungszentrum Rossendorf (FZR) e. V. is constructing a new large-scale test facility, TOPFLOW, for thermalhydraulic single effect tests. The acronym stands for transient two phase flow test facility. It will mainly be used for the investigation of generic and applied steady state and transient two phase flow phenomena and the development an...
In recent years, the simulation methods for the safety analysis of nuclear power plants have been continuously improved to perform realistic calculations. Therefore in VALCO work package 2 (WP 2), the usual application of coupled neutron-kinetic / thermal-hydraulic codes to VVER has been supplemented by systematic uncertainty and sensitivity analys...