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August 11, 2020
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Fusion Science and Technology
Latest News
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.
S. Pelloni, E.T. Chenga)
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 841-847
Neutronics and Shielding | dx.doi.org/10.13182/FST83-A22965
Articles are hosted by Taylor and Francis Online.
The U.S. Fusion Engineering Device (FED) was used as a basis to investigate the uncertainties of several neutronics performance parameters that arise due to nuclear data uncertainties. The neutron flux distribution was calculated using the discrete-ordinates transport code ANISN. Nuclear data considered were from the VITAMIN-C (DLC-41) library. Atomic displacement rate in the TF coil copper stabilizer, nuclear heating in the epoxybased insulation material and TF coil, and energy multiplication were estimated. The cross section sensitivity study was performed using the sensitivity analysis code SWANLAKE. It shows that the copper atomic displacement rate in the inboard TF coil is known within ± 24 %. The nuclear heating in the inboard insulation material and TF coil are known within ± 21 % and ± 12.5 %, respectively. The uncertainties are primarily due to the iron inelastic scattering cross sections in the 14 MeV energy range.
