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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.
U. Salmi, J. J. Wagschal, A. Yaari, Y. Yeivin
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 298-300
Technical Note | doi.org/10.13182/NSE83-A17799
Articles are hosted by Taylor and Francis Online.
Several widely used neutron transport codes approximate the fission-source matrix by accepting only a single fission-neutron spectrum, regardless of how this spectrum is selected. This approximation introduces a needless calculational error. To overcome this flaw the difference between the correct and the approximate fission source matrices should be added to the scattering matrix. This significantly reduces the calculational errors in integral parameters calculated in the k formulation of the stationary transport equation and eliminates these errors altogether when the integral parameters are calculated in the other formulations of the equation. A numerical example is provided to demonstrate these points. The reactivity k, the average neutron energy , and the ratio are calculated for a JEZEBEL-like assembly using the standard and the proposed procedures.
