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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
Nicolas Woolstenhulme, Colby Jensen, Charles Folsom, Robert Armstrong, Junsoo Yoo, Daniel Wachs
Nuclear Technology | Volume 207 | Number 5 | May 2021 | Pages 637-652
Technical Paper | doi.org/10.1080/00295450.2020.1807280
Articles are hosted by Taylor and Francis Online.
Design evaluations and thermal-hydraulic predictions were undertaken to compare three candidate options for loss-of-coolant accident (LOCA)–testing capabilities at the Transient Reactor Test facility (TREAT). These options included a small water capsule, a large natural circulation capsule, and a forced-convection water loop. All options were found to create reasonable approximations of radial temperature gradients in fuel specimens prior to blowdown to a secondary tank. Given its minimalist form factor, the small water capsule was predicted to perform remarkably well in mimicking the thermal response of a 20-pellet fuel rodlet during a postulated LOCA event, while sensitivity studies showed versatility in adjusting conditions for specific test phenomena priorities. The large natural circulation capsule predictions showed representative capsule pressure evolution but indicated it would likely struggle to capture the desired fuel temperature response in the blowdown transition, primarily due to nonrepresentative cooling as its tall water column was discharged. These results were compared to previous water loop evaluations that had shown a capability for representing ideal test conditions, especially for longer rodlet test specimens in small bundles, while being achievable in a self-contained form factor to facilitate test logistics. Considering the broader cost and capability spectrum needed to support fuel safety research, these efforts resulted in a recommendation to pursue the small water capsule for near-term data needs specific to high-burnup fuel fragmentation, while continuing detailed development of the water loop to address ultimate data needs.