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Fusion Science and Technology
Penfield and Enos: Outage planning in the COVID-19 era
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.
Shohei Matsuda, Kazunari Katayama, Motoki Shimozori, Satoshi Fukada, Hiroki Ushida, Masabumi Nishikawa
Fusion Science and Technology | Volume 67 | Number 2 | March 2015 | Pages 467-470
Proceedings of TRITIUM 2013 | dx.doi.org/10.13182/FST14-T56
Articles are hosted by Taylor and Francis Online.
F82H is a primary candidate of structural material and coolant pipe material in a blanket of a fusion reactor. Understanding tritium permeation behavior through F82H is important. In a normal operation of a fusion reactor, the temperature of F82H will be controlled below 550 °C because it is considered that F82H can be used up to 30,000 hours at 550 °C. However, it is necessary to assume the situation where F82H is heated over 550 °C in a severe accident. In this study, hydrogen permeation behavior through F82H was investigated in the temperature range from 500 °C to 800 °C. In some cases, water vapor was added in a sample gas to investigate an effect of water vapor on hydrogen permeation. The permeability of hydrogen in the temperature range from 500 °C to 700 °C agreed well with the permeability reported by E. Serra et al. The degradation of the permeability by water vapor was not observed. After the hydrogen permeation reached in a steady state at 700 °C, the F82H sample was heated to 800 °C. The permeability of hydrogen through F82H sample which was once heated up to 800 °C was lower than that of the original one.