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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
Satoshi Fukada, Y. Edao, K. Katekari, H. Okitsu, Y. Hatachi, M. Okada, K. Tamari
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 58-63
Fusion | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13397
Articles are hosted by Taylor and Francis Online.
Systems to recover tritium (T) from fusion liquid blankets of LiPb (Li17Pb83) and Flibe (Li2BeF4) under safety conditions are discussed based on available data of T transport properties. We recently performed experiments on hydrogen isotopes permeating through LiPb in Kyushu University and introduced them in the present paper. Solubilities, diffusivities and permeabilities of H and D through Li17Pb83 are determined by means of a transient permeation method. Their isotope effects between H and D in the Li-Pb eutectic alloy are found to be independent of D/H atomic ratio and a function of only temperature. Tritium recovery apparatuses of a liquid-gas counter-current flowing bed or a T permeation window are designed in the liquid blanket system composed of the primary coolant of Flibe or LiPb and the secondary coolant of He or water. Simultaneous transfer of heat and T needs new configuration in order to satisfy the necessary conditions of low T leak and high heat transfer, which make it possible to operate the blanket effectively and safely. Tritium permeation rates through the primary LiPb or Flibe breeder and secondary water or He coolant loops are estimated, which is the most important factor to operate the blanket safely.
