Reactor vessel integrity database

RVID Reactor Vessel Integrity Database (USNRC)... 

The Russian predictive embrittlement method is based primarily on test reactor data and utilizes the shift in CVN impact energy properties essentially at the 47 J temperature (PNAE, 1989). The effects of Cu, P and O (E > 0.5 MeV) are included in the method. A new local approach called the Unified Curve (similar to the Master Curve method) for assessing vessel integrity has recently has been added for structural analysis purposes (Margolin et ai, 2007). Additionally, an IAEA activity on embrittlement prediction for WWER-440 RPVs was completed (IAEA, 2005), with the published IAEA report providing recommended guidelines based on a larger database than previously available. 

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