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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
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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.
G. L. Kulcinski, P. Cousseau, R. L. Engelstad, H. Y. Khater, J. J. MacFarlane, E. A. Mogahed, R. R. Peterson, M. E. Sawan, I. N. Sviatoslavsky, P. Wang
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1641-1645
Fusion Power Plants and Economics | doi.org/10.13182/FST96-A11963186
Articles are hosted by Taylor and Francis Online.
The design of a 1,000 MWe light ion driven fusion power plant is given. Considerable progress has been made in analyzing the target performance and. its impact on the cavity design. Recent declassification actions in the U.S. have resulted in more detailed calculations that reveal a somewhat lower gain (⋍70) compared to those gains previously assumed (80-100). Methods to recover that more conservative gain from other parts of the reactor design include more efficient beam transport and higher conversion efficiencies to electricity.