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Division Spotlight
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.
Yao W. Chang, Joseph Gvildys
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 388-399
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32575
Articles are hosted by Taylor and Francis Online.
Primary containment computer codes, REXCOHEP (Lagrangian), ICECO (Eulerian), ALICE (ALE), and REXALE (ALE), developed in the Engineering Mechanics Program of Argonne National Laboratory, were validated by performing comparison with the analytical solution and experimental data. Three problems were used. The first problem deals with the propagation of shock wave in a rigid tube for which analytical solution exists. The second problem concerns the response of a simple flexible vessel to a hypothetical core disruptive accident (HCDA)-in-duced pressure loading for which experimental data exist. The experiment was performed with a well-defined and calibrated energy source. It provided reliable test data for code validation. The third problem concerns the propagation of shock wave in a three-dimensional space for which the experimental data exist. Results of the comparisons show that the Lagrangian, Eulerian, and ALE codes can all give acceptable solutions to the shock wave propagations and on the response of containment vessel to HCDA-induced pressure loading.