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September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
William T. Sha
Nuclear Science and Engineering | Volume 25 | Number 4 | August 1966 | Pages 413-421
Technical Paper | doi.org/10.13182/NSE66-A18562
Articles are hosted by Taylor and Francis Online.
A one-dimensional noniterative method for calculating the fast- and thermal-neutron flux distribution, effective neutron multiplication factor, power density, enthalpy profile, water density distribution, and steam void map of a light-water moderated reactor core is presented and programmed as a computer code — ANDREA. In this method, the spatial dependence of the neutron spectrum is accounted for explicitly. The method outlined in this paper can be used as one of the design tools for pressurized water reactor (PWR) cores as well as for boiling water reactors (BWR). The novelty of this method lies in its noniterative mathematical formulation which takes into account the nuclear-thermal interaction in a reactor channel. Fission density is directly related to heat generation and heat generation causes density changes in the coolant with subsequent formation of steam voids. The method described here is based on the fact that the above relationships are interdependent. As a result of this noniterative formulation, a significant amount of computer time is saved. Finally, it is to be noted that the method presented in this paper is primarily intended for the analysis of large power reactors.
