Comprehensive solution of the „MIDICORE” Benchmark by the KARATE and MCNP code system, Centre for Energy Research
26th Symposium of AER on VVER Reactor Physics and Reactor Safety (2016, Helsinki, Finland)
Reactor physics experiments and code validation continues
Abstract
COMPREHENSIVE SOLUTION OF THE „MIDICORE” BENCHMARK BY THE KARATE AND MCNP CODE SYSTEMGy. Hegyi, A. Keresztúri, Cs. Maráczy, I. Panka, E. Temesvári, G. Hordósy Hungarian Academy of Sciences, Centre for Energy ResearchReactor Analysis Department H-1525 Budapest 114, P.O. Box 49, Hungary hegyi.gyorgy@energia.mta.huABSTRACTThe modern 3D steady-state reactor core calculations require the modelling of the reflector, where large differences of neutronics properties between the core and reflector regions can be observed.This problem can be observed in VVER-1000 NPP also, when pin power distribution is determined by codes based on pin to pin diffusion difference method on one side and by codes based on nodal diffusion method with pin power reconstruction on the other side. To study this phenomenon, a mathematical benchmark representing a simplified sector of VVER-1000 core was defined by ŠKODA JS a.s. in cooperation with ÚJV Řež a.s. It consists of 37 fresh fuel assemblies with 4 different enrichments. The details about core basket and the geometry of explicit radial reflector are given, too.To investigate this benchmark is valuable in many reasons. The validation of the actually applied calculational methods is necessary, although the distribution of the fuel pin power is not directly measured.It is worth to see how our models which were used for VVER-440 until now can be applied for VVER-1000.The problem has been solved by MCNP and KARATE codes. Now some improvements will be presented. 26th Symposium of AER on VVER Reactor Physics and Reactor Safety 10 10 – 14 October 2016, Helsinki, Finland