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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.
Ricardo Artigas, H. E. Hungerford
Nuclear Science and Engineering | Volume 36 | Number 3 | June 1969 | Pages 295-303
Technical Paper | doi.org/10.13182/NSE69-A18727
Articles are hosted by Taylor and Francis Online.
Expressions for the neutron flux at the exit of a cylindrical duct of radius δ and length l (with λ = δ2/l2), have been found by the use of the albedo concept and by the method of single-collision sources in the duct wall, based on monoenergetic integral transport theory. In contrast with other methods of solution, the isotropic area source of radius δ at the duct entrance is not approximated by a point source, and the numerical evaluation of integrals does not impose restrictions on the values of λ. Calculation of the neutron flux at the duct exit is expedited by the use of the tables given, which are a function of the duct geometry and were generated from the numerical evaluation of the integrals that appear in the expressions for the flux. Comparison of the results as predicted by the formulas developed in this paper and those predicted by already existing formulas with the results of a stochastic neutron-transport code indicates that the formulas developed here are always in better agreement with the results of the code. For values of λ < 1, the formulas developed here differ by a maximum of ± 10%, while the existing formulas differ by a maximum of more than 100%.
