A sensitivity analysis of the stresses in the most loaded reactor coolant system components in the Krško nuclear power plant has been performed with different assumptions on the earthquake intensity and selected configurations of dynamic supports. The model of the reactor coolant system developed by the J. Stefan Institute has been used in the analysis. The results of the analysis have been supplied to the regulatory body for implementation in surveillance activities.
F.17 Transfer of existing technologies, know-how, methods and procedures into practice
COBISS.SI-ID: 19352103The main purpose was the verification of the Krško nuclear power plant Full Scope Simulator using the RELAP5 code for simulating thermal-hydraulic phenomena in nuclear plants, for the following 4 accident scenarios: — anticipated transient without scram, — small break loss-of-coolant accident, — loss of feedwater in steam generators, — steam generator tube rupture. To resolve Review of Accident Management Programme open issues, studies of possible consequences due to modified flooding procedure of the cavity and of flammable gases distribution in the containment were carried out.
F.17 Transfer of existing technologies, know-how, methods and procedures into practice
COBISS.SI-ID: 19035687The objective of the project was to develop a method for updating human reliability analysis of the Krško nuclear power plant and to apply its results to the probabilistic safety assessment of the Krško NPP. The method was developed with emphasis on the dependencies between human failure events. The method was applied to the realistic models of probabilistic safety assessment of the Krško NPP, where the experience gained from the plant simulator was also considered. The key human actions were identified and proposed as candidates for training.
F.17 Transfer of existing technologies, know-how, methods and procedures into practice
COBISS.SI-ID: 20478759The goal of the seminar was to disseminate the latest research results related to thermal fatigue of stainless steel piping connections to professionals from the utility and safety administration. Special attention was given to the phenomena, which were not taken into account during the design of the second nuclear power plant generation, but could, at certain conditions, lead to damage on the equipment. Those phenomena include stratified flows and turbulent mixing of fluids, which could in turn generate temperature and stress fields in the piping and pressure vessels.
F.18 Transfer of new know-how to direct users (seminars, fora, conferences)
COBISS.SI-ID: 19862567The conference "Nuclear Energy for New Europe 2005" was attended by 197 participants from 24 countries (80 from Slovenia and 117 from abroad). At the conference, 146 papers were presented (46 from Slovenia and 100 from abroad). The following topics related to nuclear energy were represented: - reactor physics, - nuclear fusion, - fluid mechanics and heat transfer, - nuclear thermal-hydraulics, safety analyses and severe accidents, - probabilistic safety assessment, - nuclear power plant operation, - radioactive waste management, - nuclear knowledge management.
B.01 Organiser of a scientific meeting
COBISS.SI-ID: 225157888