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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Technology
Fusion Science and Technology
May 2025
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.
Wayne R. Meier, Edward C. Morse
Fusion Science and Technology | Volume 8 | Number 3 | November 1985 | Pages 2681-2695
Technical Paper | Blanket Engineering | doi.org/10.13182/FST85-A24689
Articles are hosted by Taylor and Francis Online.
A method for optimizing the design of a fusion reactor blanket as a function of several design variables is applied to a modified version of the HYLIFE inertial confinement fusion reactor. This reactor concept uses an inner liquid lithium blanket for breeding tritium and an outer manganese-steel blanket to increase the fusion energy multiplication factor. The capital cost per unit of net electric power produced is minimized subject to constraints on the tritium breeding ratio and the radiation damage rate in the first structural wall. The optimal design has a 0.9-m-thick lithium blanket denatured to 0.1 % 6Li.