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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
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.