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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
C. J. Caldwell-Nichols, M. Glugla, L. Dörr, U. Berndt
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 216-219
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A915
Articles are hosted by Taylor and Francis Online.
The PETRA facility at the Tritium Laboratory Karlsruhe (TLK) has finished its useful life and the glove box and auxiliary systems are being refurbished. During the lifetime of PETRA the glove box became contaminated with a small amount of tritium but the source has not been positively identified. Removing large redundant components would be hazardous as this would require removing the glove box panels and thus exposing the inner surfaces to moist air which would release tritium. Over several months defined amounts of water have been introduced into the glove box daily which has liberated significant quantities of tritium which has subsequently been absorbed by the in-built tritium retention system. This technique has slowly reduced the tritium liberated at each step. The large components, such as a getter bed, catalyst bed and a permeator, have been detritiated as far as possible in-situ in readiness for disposal once it is safe to remove them from the glove box.