ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
O.K. Kveton, R.S. Matsugu, S.K. Sood
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1541-1546
Inertial Fusion Reactor Studies | doi.org/10.13182/FST92-A29939
Articles are hosted by Taylor and Francis Online.
Two separate conceptual designs of commercial fusion power plants have been developed for the U.S. Department of Energy. Inertial confinement reactor designs based on the driver systems of the KrF excimer gas laser and the heavy ion linac were developed and analyzed. The preliminary system design for reactor exhaust gas recovery and purification for tritium processing is described. The integrated design consists of a palladium-silver permeator for impurity removal, a high temperature isotope exchange reactor for impurity processing, pressure swing adsorption for tritium recovery from helium and water distillation and cryogenic distillation for isotope separation. A comparison between inertial fusion and magnetic fusion tritium systems is presented.