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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.
T. Courau, G. Marleau
Nuclear Science and Engineering | Volume 141 | Number 1 | May 2002 | Pages 46-54
Technical Paper | doi.org/10.13182/NSE02-A2265
Articles are hosted by Taylor and Francis Online.
Computation of adjoint and generalized adjoint fluxes may present some difficulties, especially when relying on the collision probability technique in transport theory. This paper proposes a simple method to compute those adjoint flux and generalized adjoint fluxes associated with homogenized and condensed cross sections. By defining a pseudo adjoint flux, one can apply an algorithm, similar to that required for the evaluation of the direct neutron flux, to adjoint flux calculations. Because of the presence of the scattering source, a multigroup iterative procedure is used in DRAGON for the direct flux solution. We show that this procedure can be easily modified in such a way that the performance of the solution algorithm is preserved for the adjoint problem. Finally, a generic adjoint algorithm is presented to deal with generalized adjoint fluxes' computation.