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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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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.
C. J. Martin, L. A. El-Guebaly
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 985-989
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1622
Articles are hosted by Taylor and Francis Online.
Loss of Coolant Accident (LOCA) and Loss of Flow Accident (LOFA) thermal simulations have been performed for the ARIES compact stellarator fusion power plant. The ARIES-CS design uses three separate coolant loops: lithium-lead (LiPb) in the blanket, helium in the blanket and the shield, and water in the vacuum vessel. The thermal response to LOCA/LOFA conditions was simulated using transient axisymmetric finite element models. In these analyses, the plasma was quenched three seconds after coolant loss, and the temperature of the chamber components subsequently increased due to the generated decay heat. Thermal simulations determined the maximum temperatures reached in the various components were below the 740°C temperature limit for the reusability of the ferritic steel structure.
