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May 31–June 3, 2026
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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.
Yosuke Abe, Tomoaki Suzudo, Shiro Jitsukawa, Tomohito Tsuru, Takashi Tsukada
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 139-144
PFC and FW Materials Technology | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14126
Articles are hosted by Taylor and Francis Online.
It is known that the presence of even a small amount of impurity in interstitial positions can, depending on temperature, have a drastic influence on the one-dimensional (1-D) motion of self-interstitial atom (SIA) loops, and thus, on the accumulation of radiation damage in materials. In this study, atomic-scale computer simulations based on a recently developed optimization technique have been performed to evaluate the binding energies of SIA loops with interstitial carbon, a vacancy-carbon (V-C) complex, and a vacancy as a function of loop size in -iron. While weak and strong attractive interactions are found when an interstitial carbon atom and a vacancy, respectively, are located on the perimeter of an SIA loop, the interactions for both quickly weaken approaching the loop center. In contrast, for a wide range of loop sizes, significantly higher binding energies are obtained between an SIA loop and a V-C complex located within the habit plane of the loop. A cluster dynamics model was developed by taking into account the trapping effects of V-C complexes on 1-D migrating SIA loops, and preliminary calculations were performed to demonstrate the validity of the assumed trapping mechanism through a comparison of the microstructural evolution with experimental data in neutron-irradiated -iron.