Portfolio of Analytical Tools for Reactor Component Integrity Assessment

Office of Nuclear Regulatory Research

The Component Integrity Branch in RES has developed a suite of computational codes and capabilities to assess nuclear reactor component integrity and failure. The FAVOR (Fracture Analysis of Vessels – Oak Ridge) and xLPR (Extremely Low Probability of Rupture) probabilistic fracture mechanics (PFM) codes are used for reactor pressure vessels and primary reactor coolant system piping, respectively, and were both developed or co-developed by RES. The Flaw Evaluation Software and LEAPOR deterministic codes are used to predict crack growth due to primary water stress corrosion cracking (PWSCC), and perform deterministic leak-before break analyses for primary water system piping.  Finally, RES has developed procedures using the eXtended Finite Element Method (XFEM) to predict PWSCC crack growth for complex geometries that cannot be analyzed using more simple methods.

Page Last Reviewed/Updated Monday, August 26, 2019