پديدآورندگان :
Zerehpoosh M. R. Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran , Pirouzmand A. pirouzm@shirazu.ac.ir Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran; , Hadad K. Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran , Ghanaatian P. Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran
كليدواژه :
Technical specifications , Surveillance Test Interval , Core Damage Frequency , SAPHIRE Code
چكيده فارسي :
In the last decades, Probabilistic Safety Assessment (PSA) has been increasingly applied to improve regulatory processes, such as risk-based inform to technical specifications (TS), test and maintenance policy optimization, and etc. In this study the risk measure of Core Damage Frequency (CDF), from the level 1 PSA is used to investigate the effect of Surveillance Test Interval (STI) extensions on nuclear power plant safety. To achieve this goal, fault tree and event tree tools for the L-LOCA initiating events in a typical VVER-1000 nuclear reactor are utilized in SAPHIRE code. The results present that while the STI varies from 672 to 1440 hours the value of CDF from L-LOCA initiating events increases from 4.274E-07to 4.951E-07.
