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HEMI Seminar: Westinghouse Electric Company

March 10, 2017 @ 3:30 pm - 4:30 pm

Reviews of the AP1000® Plant Comprehensive Vibration Assessment Program and Radioactive Materials Testing at Westinghouse Electric Company

Gregory A. Banyay & Michael R. Ickes

Westinghouse Electric Company

“The presentation provided will cover two separate topics.  First, a review of the Westinghouse AP1000 plant Comprehensive Vibration Assessment Program will be provided.  Second, unique aspects of radioactive materials testing will be presented.

The effects of flow-induced vibration (FIV) is a major design consideration for the newer generations of commercial nuclear power plants that are currently coming on line, as well as for operating plant life extensions analyses and next generation plant designs in development. FIV effects are particularly important relative to reactor vessel internals (RVI) and steam system component fatigue design and analyses. This presentation reviews the primary aspects of a CVAP from both a practical engineering perspective as well as a regulatory perspective. While differences between historical and current CVAPs are discussed, the emphasis of the discussion is on the current engineering methods used for both the analytical/numerical and measurement portions of the work needed for a successful program. Of particular interest for discussion is the need to analyze and correlate numerical predictions and measurement data from a system perspective, as well as consider interactions between major component subsystems.  Much of this review is based on the successful experience with the CVAP for the new AP1000 plant RVI. However, the review is equally applicable generically to other reactor internals design type CVAPs (e.g., Boiling Water and Small Modular Reactors).

Westinghouse’s Churchill facility specializes in handling highly radioactive materials.  The heavily shielded ‘hot’ cells are used for the examination and testing of materials from nuclear reactors and other nuclear equipment.  This work is typically in support of reactor materials reliability, research and development, and failure analyses.  This seminar will discuss how materials testing is different when handling such radioactive materials as well as results from recent investigations.”

Seminar will begin at 3:30 PM in Malone Hall, G33/35.