Deterministic and probabilistic analysis of a reactor pressure vessel subjected to pressurized thermal shocks

Abstract Both deterministic and probabilistic methods are used to analyze a reference reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs). The FAVOR code was applied to calculate the probabilities for crack initiation and failure of a RPV subjected to two PTS transients, by considering different crack types, sizes and orientations. The Master Curve methods are implemented in the FAVOR code for a more realistic consideration of fracture toughness of the irradiated RPV. The analysis shows that a postulated underclad crack is the most conservative crack assumption. Assuming shallower cracks can be more conservative than deeper ones due to the fact that both K I and K IC at the crack tip increase with crack depth. Considering the warm prestressing effect (WPS) reduces the failure probability by more than two orders of magnitude. In this analysis, the FAVOR model for the calculation of fracture toughness is more conservative than the Master Curve method. But the Master Curve method is more realistic than the FAVOR model and thus its application is recommended.

[1]  G. Qian,et al.  Effect of correlated input parameters on the failure probability of pipelines with corrosion defects by using FITNET FFS procedure , 2013 .

[2]  R. D. Cheverton,et al.  OCA-P, a deterministic and probabilistic fracture-mechanics code for application to pressure vessels , 1984 .

[3]  Guian Qian,et al.  Probabilistic leak-before-break analysis with correlated input parameters , 2013 .

[4]  J. Strosnider,et al.  VISA: a computer code for predicting the probability of reactor pressure-vessel failure. [PWR] , 1983 .

[5]  Terry L. Dickson,et al.  An updated probabilistic fracture mechanics methodology for application to pressurized thermal shock , 2001 .

[6]  G. G. Chell,et al.  A theory of warm prestressing: experimental validation and the implications for elastic plastic failure criteria , 1981, International Journal of Fracture.

[7]  Markus Niffenegger,et al.  Probabilistic analysis of pipelines with corrosion defects by using FITNET FFS procedure , 2011 .

[8]  Naoki Soneda,et al.  Benchmarking Studies of Probabilistic Fracture Mechanics Analysis Code, PROFMAC-II, for Assessing Pressurized Thermal Shock Events of Reactor Pressure Vessel Integrity Issues , 1996 .

[9]  D. A. Curry,et al.  A micromechanistic approach to the warm pre-stressing of ferritic steels , 1981 .

[10]  Yinsheng Li,et al.  Development of a PFM code for evaluating reliability of pressure components subject to transient loading , 2001 .

[11]  V. F. González-Albuixech,et al.  Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions , 2014 .

[12]  J. Newman,et al.  Stress-intensity factor equations for cracks in three-dimensional finite bodies subjected to tension and bending loads , 1984 .

[13]  Markus Niffenegger,et al.  The proper use of thermal expansion coefficients in finite element calculations , 2012 .

[14]  V. F. González-Albuixech,et al.  In-plane and out-of-plane constraint effects under pressurized thermal shocks , 2014 .

[15]  Hiroto Itoh,et al.  Development of probabilistic fracture mechanics analysis codes for reactor pressure vessels and piping considering welding residual stress , 2010 .

[16]  Guian Qian,et al.  Integrity analysis of a reactor pressure vessel subjected to pressurized thermal shocks by considering constraint effect , 2013 .

[17]  Tapio Planman,et al.  Guidelines for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity in Nuclear Power Plants , 2005 .

[18]  Guian Qian,et al.  Probabilistic fracture assessment of piping systems based on FITNET FFS procedure , 2011 .

[19]  Shengjun Yin,et al.  Fracture Analysis of Vessels. Oak Ridge FAVOR, v06.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations , 2007 .

[21]  Kim Wallin Master Curve implementation of the warm pre-stress effect , 2003 .

[22]  Guian Qian,et al.  Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks , 2013 .