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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.
Dong-Jun Kim, Seong Dae Park, Dong Won Lee, Mu-Young Ahn
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 760-765
Technical Note | dx.doi.org/10.1080/15361055.2017.1350487
Articles are hosted by Taylor and Francis Online.
After Conceptual Design (CD) Approval, Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) design is being updated for the preparation of the preliminary design phase, in which the manufacturability is the main concern based on the TBM-set model of CD phase. The major design parameters at the preliminary design phase were introduced. According to these parameters, the design of the main components such as first wall (FW), side wall (SW), and the breeding zone (BZ) was updated through the thermal-hydraulic analysis with ANSYS CFX v14.5. Also, the detailed design was performed on the back manifold (BM), TBM-shield, and the connecting supports. The internal channels for the He coolant and purge gas are designed in BM, in which the characteristics of the He channel were analyzed to meet the requirements of the temperature. The design concept of the connecting supports was described. The design of the TBM-shield is updated in order to simplify production and assembly.