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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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!
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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.
Shigeo Numata, Yasuhiko Fujii, Makoto Okamoto
Fusion Science and Technology | Volume 19 | Number 1 | January 1991 | Pages 140-145
Technical Paper | Safety/Environmental Aspect | doi.org/10.13182/FST91-A29323
Articles are hosted by Taylor and Francis Online.
Depth profiles of tritiated water in concrete walls measured in a heavy water reactor are analyzed using a diffusion model. The apparent diffusion coefficient of tritiated water in concrete made with a standard mixing proportion is 3.3 × 10−11 m2/s. In addition to the primary diffusion mechanism, there is evidence of a second mechanism, possibly a fast diffusion process. The diffusion model can be applied to tritiated water penetration into concrete when the concrete walls of fusion reactors are exposed to air containing tritiated water vapor. In the heavy water reactor, the average concentration of tritiated water in the air over 20 yr is estimated to be ∼2.0 × 10−2 Bq/cm3. The tritium inventory in concrete is ∼1.0 × 107 Bq/m3 in the region <0.65 m deep. A 0.2-m-thick concrete wall is sufficient to prevent tritium release into the environment from exceeding the regulatory limit.