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