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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
H. Zhang, A. Ying, M. Abdou
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 362-367
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-936
Articles are hosted by Taylor and Francis Online.
In this paper the problem of tritium transport in PbLi (Lead-Lithium) blankets has been studied and analyzed by means of our recently developed computational models. Several simulations are performed by incorporating the geometric configurations of the PbLi blankets including both DCLL (Dual Coolant Lead Lithium) and HCLL (Helium Cooled Lead Lithium) blankets. Tritium permeation loss percentage from the HCLL concept is about one order of magnitude higher than from the DCLL concept (~ 17%. vs. 1.2%). Sensitivity study also shows that the most relevant factors on tritium permeation are: 1) the level of tritium solubility in PbLi, 2) the gap velocity of the liquid metal in a DCLL blanket, 3) Hartmann number, and 4) the FCI (Flow Channel Insert) electrical conductivity.