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.
Masao Kitamura, Eishi Ibe, Shunsuke Uchida, Takashi Honda, Glauco Romeo, Robert L. Cowan
Nuclear Science and Engineering | Volume 89 | Number 1 | January 1985 | Pages 61-69
Technical Paper | doi.org/10.13182/NSE85-A17883
Articles are hosted by Taylor and Francis Online.
60Co accumulation on boiling water reactor (BWR) primary cooling pipings. To demonstrate the treatment effect, test specimens, which had been exposed to simulated BWR water in an autoclave (temperature, 286 °C; pH, 7; oxygen concentration, 200 ppb) for up to 200 h, were installed in the Hatch-2 inplant loop and their 60Co deposition amounts were compared with those of as-received specimens. Preoxidation treatment for 200 h resulted in deposits of about one-fourth those of as-received specimens. It was estimated that the maximum amount of 60Co deposited on primary piping during the entire plant operation life (30 yr) would be reduced to about one-half of that without preoxidation treatment if the 60Co concentration in the reactor water was constant.