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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Akira Oikawa, Naoyuki Miya, Kozo Kodama, Takashi Umehara, Takeshi Yamazaki, Kei Masaki, Isamu Akiyama, Kozo Matsushita, Nobuyuki Hosogane
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 612-616
Device, Facility, and Operation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22661
Articles are hosted by Taylor and Francis Online.
Effluent of tritium in vacuum exhaust in JT-60 through the stack to environment always remains a level below detectable level (<10−5Bq/cm3 at the stack, <10−7Bq/cm3 at the site boundary). Though tritium concentration of drain water is below the limit of regulations of the local agreement and the law, small tritium contamination in the facility drain and in the rain drain of stack appeared occasionally. For a scheduled maintenance work of the in-vessel components, following an annual deuterium plasma discharge campaign, a 4-week no-deuterium (H or He) plasma discharge campaign and the succeeded ventilation by room air allow to reduce tritium on the interior surface of in-vessel components. This cleaning up shots and air introduction allowed workers to enter into the vacuum vessel. Air blow well tends to remove surface tritium elements and would be necessary before disassembly and replacement of components on vacuum pumping lines.