ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
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.
Takayuki Terai, Satorn Tanaka, Yoichi Takahashi
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2143-2148
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24600
Articles are hosted by Taylor and Francis Online.
In-situ tritium release behavior from Li2O powder has been investigated under neutron irradiation at high temperatures. It was found that the chemical form of the released tritium depended strongly on the experimental conditions such as pre-treatment (dehumidification) of the sample and the H2 addition to the sweep gas of helium. Water-soluble component was observed to be a main species from the sample pre-dried in N2 stream at 800°C for 3 days, while water-insoluble component had fairly large proportion on the sample pre-dried for 5 days. In the case of He-4%H2 sweep gas, more than 90% of released tritium was water-insoluble even for the sample pre-dried for 3 days. Tritium recovery rate was also accelerated by H2 addition. These experimental results showed that the oxygen activity of the experimental system essentially affected to tritium release behavior from Li2O sample.