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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Richard Simms
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 257-266
Technical Paper | Fuel | doi.org/10.13182/NT80-A32529
Articles are hosted by Taylor and Francis Online.
A systematic study of fuel motion in TREAT tests related to liquid-metal fast breeder reactor (LMFBR) safety has been conducted for recent experiments containing typical LMFBR fuel Net axial fuel motion is characterized by changes in fuel reactivity worth using representative LMFBR fuel-worth distributions. Fuel-motion data from these experiments, when converted to changes in equivalent fuel worth, permit interpretations based on the experimental results to be related to specific LMFBR safety issues. Verification of fuel-motion-model predictions in accident-analysis codes can also be greatly simplified by comparisons with the experimental results using the equivalent fuel-worth changes as the principal figure of merit.
