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August 2025
Latest News
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.
Mohamed E. Sawan
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 766-770
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9002
Articles are hosted by Taylor and Francis Online.
Data for 40 of the 71 isotopes/elements in FENDL-2.1 were taken from ENDF/B-VI.8. Following the release of ENDF/B-VII.0 we performed a preliminary assessment for changes made in data of these 40 isotopes/elements. We compared the relevant cross sections in the two libraries. In addition, we carried out MCNP calculations for a calculational benchmark representative of an early ITER design that was utilized during the FENDL development process. In addition, we performed 3-D calculations for an inertial fusion power plant conceptual design. It is concluded that modifying FENDL-2.1 to include the most recent ENDF/B-VII.0 is not urgently needed for ITER analysis. On the other hand, the larger changes in calculated ICF target neutronics parameters and tritium breeding ratio confirm the need for updating FENDL-2.1 for use in analysis of fusion systems beyond ITER. Additional calculations are in progress for integral experimental benchmarks to fully understand the impact of data changes introduced in ENDF/B-VII.0.