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Penfield and Enos: Outage planning in the COVID-19 era
Penfield
Enos
Energy Harbor’s Beaver Valley plant, located about 34 miles northwest of Pittsburgh, Pa., was one of many nuclear sites preparing for a scheduled outage as the coronavirus pandemic intensified in March. The baseline objective of any planned outage—to complete refueling on time and get back to producing power—was complicated by the need to prevent the transmission of COVID-19.
While over 200 of the plant’s 850 staff members worked from home to support the outage, about 800 contractors were brought in for jobs that could only be done on-site. Nuclear News Staff Writer Susan Gallier talked with Beaver Valley Site Vice President Rod Penfield and General Plant Manager Matt Enos about the planning and communication required.
Beaver Valley can look forward to several more outages in the future, now that plans to shut down the two Westinghouse pressurized water reactors, each rated at about 960 MWe, were reversed in March. “The deactivation announcement happened in the middle of all our planning,” Enos said. “It’s a shame we haven’t had a chance to get together as a large group and celebrate that yet.”
While the focus remains on safe pandemic operations, the site now has two causes for celebration: an outage success and a long future ahead.
Daeseo Koo, Jungmin Lee, Jongchul Park, Hyun-Goo Kang, Min Ho Chang, Sei-Hun Yun, Seungyon Cho, Ki Jung Jung, Seungwoo Paek, Hongsuk Chunga
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 435-438
Proceedings of TRITIUM 2013 | dx.doi.org/10.13182/FST14-T48
Articles are hosted by Taylor and Francis Online.
Korea has been developing nuclear fusion fuel storage and delivery system (SDS) technologies including a basic scientific study on hydrogen storage. To develop nuclear fusion technology, it will be necessary to store and supply hydrogen isotopes needed for Tokamak operation. SDS is used for storing hydrogen isotopes as a metal hydride form. We designed and fabricated a small-scale getter bed of zirconium cobalt (ZrCo). The rapid hydriding of tritium is very important not only for safety reasons but also for the economic design and operation of the SDS. The effect of the initial absorption temperatures on the hydriding of ZrCo was measured and analyzed. The experimental results of the hydrogen pressure of hydriding (ZrCoH2.8) at various cooling temperatures are in agreement with the calculated values using numerical modeling equations. The effect of a helium blanket on hydriding was measured and analyzed. The experimental results of the hydriding with 0 %, 4%, and 8% of helium concentration are in agreement with the calculated values based on numerical modeling equations.
