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From operator to entrepreneur: David Garcia applies outage management lessons
David Garcia
If ComEd’s Zion plant in northern Illinois hadn’t closed in 1998, David Garcia might still be there, where he got his start in nuclear power as an operator at age 24.
But in his ninth year working there, Zion closed, and Garcia moved on to a series of new roles—including at Wisconsin’s Point Beach plant, the corporate offices of Minnesota’s Xcel Energy, and on the supplier side at PaR Nuclear—into an on-the-job education that he augmented with degrees in business and divinity that he sought later in life.
Garcia started his own company—Waymaker Resource Group—in 2014. Recently, Waymaker has been supporting Holtec’s restart project at the Palisades plant with staffing and analysis. Palisades sits almost exactly due east of the fully decommissioned Zion site on the other side of Lake Michigan and is poised to operate again after what amounts to an extended outage of more than three years. Holtec also plans to build more reactors at the same site.
For Garcia, the takeaway is clear: “This industry is not going away. Nuclear power and the adjacent industries that support nuclear power—and clean energy, period—are going to be needed for decades upon decades.”
In July, Garcia talked with Nuclear News staff writer Susan Gallier about his career and what he has learned about running successful outages and other projects.
Jose-Carlos Rivas, Javier Dies
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 825-829
Computational Tools, Modeling & Validation | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12488
Articles are hosted by Taylor and Francis Online.
In this contribution, an upgraded model for plasma-wall interaction in the AINA code is presented. The AINA code is a comprehensive hybrid code comprising a global balance plasma dynamics model and a radial and poloidal thermal analysis of in-vessel components. AINA is an evolution of the SAFALY code, which was initially adopted to assess ITER EDA plasma safety events and quantitatively investigate plasma instability events in nuclear fusion reactors such as ITER.The new erosion code module includes algorithms for the most relevant plasma wall interaction phenomena that will take place in the ITER vessel during the steady state of the normal operation. Physical sputtering, radiation enhanced sublimation (RES), and chemical erosion algorithms have been added to the previous thermal sublimation algorithm. The erosion results from these models have been benchmarked with results for ITER normal operation from the B2-Eirene code.The new erosion model had to be tested with external data for particle fluxes over the wall, because the AINA code does not presently have the ability to model those particle fluxes. However, with the new results, the impurity transport model parameters have been re-calibrated and some useful conclusions have been extracted.