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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
Younggil Jin, Hyun-Su Kim, Sun-Taek Lim, Jin-Young Lee, Nam-Kyun Kim, Jae-Min Song, Gon-Ho Kim
Fusion Science and Technology | Volume 68 | Number 1 | July 2015 | Pages 113-119
Technical Paper | Open Magnetic Systems 2014 | doi.org/10.13182/FST14-886
Articles are hosted by Taylor and Francis Online.
The effect of interface diffusion between tungsten and graphite on embrittlement has not been examined over the tungsten ductile-brittle transition temperature. To analyze interface embrittlement with tungsten carbide (WC) formation and hardness, a reactive diffusion barrier model was adapted to clarify the roles of leak rate, lag time, and impurity. Plasma-sprayed tungsten (PS-W) on graphite with molybdenum interlayer (diffusion barrier) was fabricated using plasma-spray. The carbon concentration and hardness were measured using energy-dispersive X-ray spectroscopy and micro-indentation after furnace experiments relevant to plasma-facing component upper limit temperature (1470 K). The lag time and the leak rate were determined by the model with different impurity amounts (10-30 at. %) and barrier thicknesses (1-40 μm). It is worth noting that the lag time determines embrittlement threshold time because it delays the onset of diffusion, and it is expanded with thicker barrier and impurity (0.07-21000 ms). The leak rate represents the embrittlement rate since it limits the diffusion flux, and it does not depend on impurity but on barrier thickness. Diffusion-induced interface embrittlement was measured and estimated based on WC fraction. The embrittlement can be spatially expanded with time, suggesting that interface embrittlement can be severe for KSTAR long-term operation.