Patent ID: 7637653
Filing Date: 2009-12-29
Classification: F01K,F22B,G06Q,Y02P

Abstract:
1. A method to determine corrective actions of a steam generator of an operating nuclear power plant, comprising: modeling heat transfer characteristics of deposits over the heating surface of a steam generator tubing by analytically deriving descriptive model parameters, the model parameters comprising the deposit thickness, δ, the deposit porosity, ε, the deposit copper content, Cu, the effective fraction, K, of the deposit full thickness conductive heat transfer resistance, which lies between the tubing and deposit steam channel, and the deposit tortuosity, τ, wherein individual parameters δ, ε, Cu, K, and τ evolve in time as a function of a B parameter as follows: wherein M identifying a set of preventative and/or corrective maintenance alternatives for the steam generator to accomplish steam generator deposit objectives, based on the modeling; determining through the modeling a power production impact of the set of preventative and/or corrective maintenance alternatives for the steam generator; and initiating a maintenance alternative on the steam generator, based on the determination of the power production impact of the set of preventative and/or corrective maintenance alternatives for the steam generator.