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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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 News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.