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
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
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
M. Iseli
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 629-633
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1004
Articles are hosted by Taylor and Francis Online.
Knowledge of the levels of tritium in the First Wall (FW) coolant and components of ITER is important for public and operator safety and waste management. To overcome the large uncertainty of plasma wall interaction and physical properties, a basic set of properties is theoretically calculated for the dissolved tritium atoms in a perfect Beryllium (Be) lattice. These properties are combined with models for tritium trapping by lattice imperfections including the equilibrium conditions between gaseous, dissolved and trapped hydrogen isotopes. The 3 models for trapping by impurities, radiation damage and surface defects are adjusted to experimental solubilities, to tritium release experiments from irradiated samples and to outgassing of hydrogen isotopes from the JET FW. An elastic lattice model evaluates the activation energy of diffusion. For the calculations, the code DIET (Diffusion, Implantation and Equilibrium Trapping) was developed, which includes tritium trapping with time-dependent trap concentrations of multiple trap sites. The sensitivity analysis, with the expected deviations from the basic properties provides confidence that tritium permeation is below one gram in ITER for a neutron load of 0.3 MWa/m2 within 10 years.