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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Hilbert Christensen
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 358-364
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3768
Articles are hosted by Taylor and Francis Online.
A previously developed radiolysis model has been used to simulate experiments from four laboratories. The source strengths in the experiments with UO2, doped with 238Pu, were 0.01, 0.1, and 1 Ci/g. The agreement was good with the experimental results of Stroes-Gascoyne et al. for their sample with 0.1 Ci/g. Their sample containing 0.01 Ci/g gave a factor-of-3-higher calculated corrosion rate compared with the experimental rate. In the experiments of Cobos et al. and of Kelm and Bohnert, using alpha-doped UO2, the calculated corrosion rates were somewhat lower than the experimental rates. However, recent experiments by Rondinella et al. using UO2 with 10% doped 233U gave considerably lower corrosion rates in good agreement with the model. The calculated corrosion rates for the same source strength were about the same for the experiments by Stroes-Gascoyne et al., Kelm and Bohnert, and Cobos et al. However, the experimental rates varied considerably. The agreement was not good with experiments using Pu(VI) dissolved in solution, in which case the calculated corrosion rate was ten times or more than ten times lower than the experimental rate. The reason for this disagreement could be a chemical effect of Pu(VI) in the solution.