Analysis and Discussion for Fast Fracture of Reactor Pressure Vessel （RPV） Based on RCC-M Code

The fast fracture analysis and evaluation methods were compared and discussed in appendix ZG of RCC-M code Ver.2000 and Ver.2007. Comparison shows that the appendix ZG 2007 edition has a wider scope of application, the process of analysis in Ver.2007 is relatively simplified and the consideration in Ver.2007 are more comprehensive for the material aging. Taking the analysis of the fast fracture of the reactor core as an example, the sensitivity of the orientation parameters of the reference defects is analyzed, and the evaluation results of the two versions were compared. The results show that the margin of the evaluation results of Ver.2007 appendix ZG is much larger and the limitation of the P-T curve of the reactor pressure vessel is enlarged, and the operation space of the nuclear power plant is expanded