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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Y. Asakura et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 401-404
Technical Paper | Tritium Science and Technology - Tritium Measurement, Monitoring, and Accountancy | doi.org/10.13182/FST05-A953
Articles are hosted by Taylor and Francis Online.
In order to realize the deuterium plasma experiments by using the Large Helical Device (LHD), NIFS is planning to install the system for tritium recovery from exhaust gas and effluent liquid. With the case of adopting generally used tritium recovery systems, NIFS has also made the development plans for the compact and less waste generating recovery system by applying the latest technologies such as tritium gas extraction with a proton conducting ceramic and tritiated water vapor removal with a membrane type dehumidifier. Applicability of these new technologies on the tritium recovery system for the LHD deuterium plasma experiment are evaluated quantitatively using the latest experimental data.Mock-up tests of the membrane type dehumidifier are carried out and verified the way of automated operation and stable dehumidifier performance during a long time operation.