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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Eugene Goldberg, Ronald L. Barber, Norman A. Bonner, Clyde M. Griffith, David R. Nethaway, Robert C. Haight
Nuclear Science and Engineering | Volume 94 | Number 2 | October 1986 | Pages 120-135
Technical Paper | doi.org/10.13182/NSE86-A27447
Articles are hosted by Taylor and Francis Online.
A large cylindrical assembly of 6LiD was irradiated by neutrons from a high-intensity deuterium-tritium source. Small samples of 6Li, 7Li, and 6LiH, all encapsulated in lead, were positioned along the assembly axis and served as indicators for 4He and tritium production. The amount of 4He was determined by isotope dilution mass spectrometry while the tritium content of the 6LiH wafers was measured by proportional counting of gas samples. Careful comparison of the results with TART Monte Carlo calculations showed excellent agreement. For 4He generation, the experimental values were 1.01 ± 0.06 times those of the calculations, while for tritium the ratio was 1.055 ± 0.07.
