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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
T. Hayashi, S. Konishi, H. Nakamura, M. Inoue, K. Hirata, K. Okuno, Y. Naruse, J.W. Barnes, W. Harbin, R. Wilhelm, M. King, J.R. Bartlit, J.L. Anderson
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1979-1983
Material and Tritium | doi.org/10.13182/FST92-A30011
Articles are hosted by Taylor and Francis Online.
The JAERI (Japan Atomic Energy Research Institute) Fuel Cleanup system (JFCU), which accepts simulated fusion reactor exhausts and produces pure hydrogen isotopes and tritium-free waste, was tested at the Tritium Systems Test Assembly (TSTA) with gram levels of tritium in 1991 under the US/Japan collaboration program on Fusion Technology. In 1991, the JFCU system integrity and safe operation with gram level tritium were demonstrated. Component performances with tritium were also measured and further subjects for R&D were uncovered. The resident tritium inventory of the JFCU was evaluated at about six grams during TSTA loop operation with a DT (1:1) mixture. After these tests, all tritium used in the experiments was recovered as hydrogen isotopes gases.