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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.
L. El-Guebaly, M. Harb, A. Davis, J. Menard, T. Brown
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 354-361
Technical Paper | dx.doi.org/10.1080/15361055.2017.1333864
Articles are hosted by Taylor and Francis Online.
The Fusion Nuclear Science Facility (FNSF) is viewed as an essential element of the US developmental roadmap to fusion energy. The spherical tokamak-based FNSF has been designed through a national collaborative effort led by the Princeton Plasma Physics laboratory. High-temperature superconducting (HTS) magnets are potentially attractive for such applications. Among other aspects, the magnet shielding and tritium breeding assessments represent key elements for achieving the design engineering objectives. Numerous inboard shielding and cooling materials have been examined to select an optimal shield that protects the inboard HTS magnet and in the meanwhile enhances the outboard breeding. The breeding blanket of choice is the dual-cooled lead lithium (DCLL) blanket. Our 3-D neutronics model included all blanket internals in great details along with nine specialized ports for blanket testing, materials testing, plasma heating, and current drive. The inclusion of a thin DCLL blanket on the inboard side was deemed necessary to achieve an overall tritium breeding ratio in excess of unity.