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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
M. C. Billone, Y. Y. Liu
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 881-886
Tritium | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40144
Articles are hosted by Taylor and Francis Online.
Models are developed to describe the steady-state percolation of tritium through the solid-breeder interconnected porosity to the purge stream, convection of tritium by the helium purge stream, and permeation of tritium through the structural material to the primary coolant system. Important parameters in the models are tritium generation rate, breeder microstructure, tritium species in the gas phase, temperatures, tritium diffusivities and permeabilities, and effectiveness of oxide barriers. The models are used to perform calculations for fusion-blanket conceptual designs. The results indicate that for isotopic swamping of the purge stream with protium and relatively high oxide impedance factors (∼100 for nonbreeder-side surfaces) the leakage rate from the blanket can be limited to less than 100 Ci/day for reasonable purge flow rates and pressure drops. However, for lower impedance factors and/or for decreased protium partial pressure in the purge, problems do arise with limiting the tritium leakage.