ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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June 2025
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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.
John R. Phillips, Barry K. Barnes, Thomas R. Bement
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 21-29
Technical Paper | Reactor | doi.org/10.13182/NT46-21
Articles are hosted by Taylor and Francis Online.
The correlation of 134Cs/137Cs to burnup in irradiated fast reactor fuel pins was investigated using nondestructive precision gamma-ray scanning. This correlation was significant within individual subassemblies provided certain basic assumptions are satisfied. The calibration line must be calculated for each assembly based on independently measured burnup values. Differences in calibration lines for separate subassemblies are highly significant (P < 0.005). Therefore, application of this technique for the nondestructive measurement of burnup in fast reactor fuels has serious problems that must be considered.
