Passive system reliability in the nuclear power plants (NPPs) using statistical modeling

The probabilistic safety assessment (PSA) has been studied for the very high temperature reactor (VHTR). There is a difficulty to make the quantification of the PSA due to the deficiency of the operation and experience data. So, it is necessary to use the statistical data for the basic event. The physical data of the non-linear fuzzy set algorithm are used to quantify the designed case. The mass flow rate in natural circulation is investigated. In addition, the potential energy in the gravity, the temperature and pressure in the heat conduction, and the heat transfer rate in the internal stored energy are investigated. The values in the probability set and fuzzy set are compared for the failure explanation. The result shows how to use the newly made probability of the failure in the propagations. The failure frequencies, which are made by the GAMMA (GAs Multi-component Mixture Analysis) code, are compared with four failure frequencies by probabilistic and fuzzy methods. The results show that the artificial intelligence analysis of the fuzzy set could improve the reliability method than that of the probabilistic analysis.