ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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 Science and Engineering
June 2025
Nuclear Technology
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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.
Joseph A. Naser, Bal Raj Sehgal, Lance J. Agee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 311-321
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32776
Articles are hosted by Taylor and Francis Online.
The capabilities of the RETRAN-02 code have been extended to allow it to perform pressurized water reactor anticipated transient without scram (ATWS) calculations. In particular, the steam property functional fits have been extended to 41.4 MPa (6000 psia) and a better steam generator simulation capability using local conditions heat transfer has been incorporated. The local conditions heat transfer model and alternate steam generator modeling techniques are described. A loss-of-feedwater ATWS was performed with RETRAN-02 and compared with vendor calculations with excellent agreement.
