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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.
Anselmo T. Cisneros, Dan Ilas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 331-340
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A19422
Articles are hosted by Taylor and Francis Online.
The Advanced High-Temperature Reactor (AHTR) is a 3400-MW(thermal) fluoride salt-cooled high-temperature reactor that uses coated particle fuel compacted into slabs rather than spherical or cylindrical fuel compacts. Simplified methods are required for parametric design studies to perform burnup analysis on the entire feasible design space. These simplifications include fuel homogenization techniques to increase the speed of neutron transport calculations and equilibrium depletion analysis methods to analyze systems with multibatch fuel management schemes.This paper presents three elements of significant novelty. First, the reactivity-equivalent physical transformation (RPT) methodology usually applied in systems with cylindrical and spherical geometries has been extended to slab geometries. Second, implementing this RPT homogenization, a Monte Carlo-based depletion methodology was developed to search for the maximum discharge burnup in a multibatch system by iteratively estimating the beginning of equilibrium cycle composition and sampling different discharge burnups. This iterative equilibrium depletion search method fully defines an equilibrium fuel cycle (keff, power, flux, and composition evolutions) but is computationally demanding. Therefore, an analytical method, the nonlinear reactivity model, was developed so that single-batch depletion results could be extrapolated to estimate the maximum discharge burnup in systems with multibatch fuel management schemes.