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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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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. R. Bierman, E. D. Clayton
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 131-144
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32730
Articles are hosted by Taylor and Francis Online.
A series of criticality experiments with 2.35 and 4.31 wt%o 235U-enriched UO2 rods in water was performed to provide well-defined benchmark-type data on thick steel reflecting walls. For each fuel enrichment, the critical separation between three subcritical fuel clusters was observed to increase as 178.5-mm-thick reflecting walls of reactor-grade steel was moved toward the fuel. This increase was observed for fuel clusters having an undermoderated water-to-fuel volume ratio of 1.6 and for fuel clusters having near optimum neutron moderation (2.92 for the 2.35 wt% 235U-enriched fuel and 3.88 for the 4.31 wt% 235Uenriched fuel). In all cases the critical separation between fuel clusters increased to a maximum as the steel walls were moved toward the fuel clusters. This maximum effect was observed with ∼10 mm of water between the fuel clusters and the steel reflecting walls. As this water gap was decreased, the critical separation between the fuel clusters also decreased slightly. Measurement data were also obtained for each enrichment with neutron absorber plates between the fuel clusters having the 1.6 water-to-fuel volume ratio. During these measurements, the steel reflecting walls were at the near optimum distance from the fuel clusters. The fixed neutron absorbers for which data were obtained include Type 304L stainless steel, borated Type 304L stainless steel, copper, copper containing 1 wt% cadmium, cadmium, and two tradename materials containing boron (Boral and Boroflex).