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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.
Randall D. Manteufel, Neil E. Todreas
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 421-440
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34941
Articles are hosted by Taylor and Francis Online.
An effective thermal conductivity (keff) and an edge thermal conductance (hedge) model are developed for the interior and edge regions of a spent-fuel assembly residing in an enclosure. The model includes conductive and radiative modes of heat transfer. Predictions using the proposed keff/hedge model are compared with five sets of experimental data for validation. The model is compared with predictions generated by the engine maintenance, assembly, and disassembly (E-MAD) and Wooton-Epstein correlations, which represent the state of the art in this field. The model is applied to a typical pressurized water reactor and a typical boiling water reactor spent fuel assembly, and a set of both nonlinear and linear formulations of the model are derived. The proposed model is based on rigorous models of the governing heat transfer mechanisms and can be applied to a large range of assembly and enclosure types, enclosure temperatures, and assembly decay heat values. The proposed model is more accurate than comparable lumped correlations and is more amenable for simple, repetitive design applications than other detailed numerical models.