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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
Fred A. Kloverstrom, Richard M. R. Deck, Arnold J. Reyenga
Nuclear Science and Engineering | Volume 8 | Number 3 | September 1960 | Pages 221-225
Technical Paper | doi.org/10.13182/NSE60-A25802
Articles are hosted by Taylor and Francis Online.
A series of critical measurements on unreflected systems, fueled by thin enriched uranium (93.2%) foils, is described. Fuel density is varied by use of different foil thicknesses and spacings between foils. Five fuel densities have been used which correspond to atomic BeO/U235 ratios from 246 to 7660. For three of these ratios, the fuel foil thickness was varied to find effects of self-shielding and flux depression on the critical dimensions.
