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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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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.
S. Sharafat, C. P. C. Wong, E. E. Reis, THE ARIES TEAM
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 901-907
Advanced Reactor | doi.org/10.13182/FST91-A29459
Articles are hosted by Taylor and Francis Online.
The ARIES-I reactor is a 1000-MWe, DT-burning tokamak reactor that combines present-day physics with advanced engineering technology such as high-field superconducting magnets and low-activation SiC composites as structural material. Recent developments in the manufacturing of fiber-reinforced ceramics for improved mechanical properties make these materials promising candidates for future fusion reactors. The low-activation, low-afterheat characteristics of SiC can lead to an inherently safe reactor design with a Class-C waste-disposal rating. The first wall, blanket, shield, and the divertor all use SiC composite as structural material and helium as coolant. The thermomechanical behavior of the first wall is analyzed using the ANSYS finite-element code. The analysis shows that the first wall performs well below suggested allowable stress and temperature limits. Although the finite element analysis assumes idealized conditions, the results indicate that SiC composite materials could perform well under specified operating conditions. Given the potential safety and environmental advantages of SiC composites, the current large-scale developmental efforts taking place outside of the fusion community should be complemented by R&D efforts that focus on neutron- and ionizing-irradiation effects on SiC composite materials.