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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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.