Determination of engineering safety factor -routine in Hungary (a methodology for the normal operation local power engineering safety factors)

Z. Szécsényi, L. Korpás, G. Bóna, Paks NPP Ltd, Hungary & A. Keresztúri KFKI AEKI, Hungary

20th Symposium of AER on VVER Reactor Physics and Reactor Safety (2010, Hanasaari, Espoo, Finland)
Engineering factors


From the late nineties Paks Nuclear Power Plant ? in collaboration with KFKI Atomic Energy
Research Institute (KFKI AEKI) ? is developing a system for determining the normal
operation local power engineering safety factors. The system is based on a Monte Carlo
sampling of the uncertain model input parameters. Additionally, the comparison of the
calculation to the in-core measurements plays essential role for determining some important
input parameters. By using new fuel types and the corresponding more recent detailed
technological data, the applied method is being improved from time to time. Presently, the
actually used and authorized engineering safety factors at Paks NPP are determined by using
this method.
In the paper, the system?s main properties are described (not going beyond the possible
extent). The main points are as follows:

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