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Division Spotlight
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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
T. Tanabe, K. Miyasaka, K. Sugiyama, K. Masaki, K. Kodama, N. Miya
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 877-881
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22710
Articles are hosted by Taylor and Francis Online.
Tritium distributions on the graphite tiles used as plasma facing tiles in divertor tiles, dome units, and the baffle plates of JT-60U were successfully measured. The highest tritium level was found at the top of the dome or the private region and the outer baffle plates, where the plasma did not hit but the distance from the plasma was the shortest. For the divertor tiles, the tritium retention was very small. Such tritium distribution observed in JT-60U tiles can be well explained by the homogeneous implantation of rather high energy tritium and thermal release due to the heat load.