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
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
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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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.
Munir Ahmad, S. L. Graham, S. M. Grimes, H. Satyanarayana, S. K. Saraf, and S. Stricklin
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 311-319
Technical Paper | doi.org/10.13182/NSE85-A17772
Articles are hosted by Taylor and Francis Online.
Total cross sections for the emission of protons and alpha particles have been measured for 9.4- and 11-MeV neutrons incident on a 4.11 mg/cm2 thick Type 316 stainless steel target. A newly developed charged-particle time-of-flight spectrometer was used to obtain (n, xp) and (n, xα) cross-section data. The measured gas-production cross sections have been compared with the values predicted on the basis of measured or calculated cross sections of the constituent materials.