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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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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.
R. G. Clemmer, D. K. Sze, P. E. Blackburn, E. VanDeventer, V. A. Maroni
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1612-1618
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29572
Articles are hosted by Taylor and Francis Online.
A 2:1 mixture of LiF and BeF2 (FLIBE), is a potential tritium breeder material for fusion reactors, in particular, the Advanced Safe Pool Immersed Reactor (ASPIRE). A limited experimental campaign was conducted in an effort to test the postulates of the ASPIRE concept: namely, that MoF6 is effective in controlling the tritium species by maintaining the TF form and that MoF6 can serve as a source to plate out Mo on surfaces, thereby making the FLIBE system compatible with the corrosive TF. It was demonstrated experimentally that successive additions of MoF6 achieved quantitative (i.e., greater than 99.7%) conversion of H2 to HF. Thus, MoF6 is effective in controlling the tritium species. The degree of conversion of H2 to HF demonstrates that HF does not attack MO to form H2. This supports the postulate that the system is compatible with Mo. Thus, if it were possible to plate out and maintain a coating of Mo on all surfaces in contact with the FLIBE system, the ASPIRE concept could work. Thermodynamic calculations also confirmed that MoF6 should be capable of quantitatively (>99.9%) converting H2 to HF. There is both experimental and theoretical evidence that a number of MoFx species are present in both the gas phase and the FLIBE solution.