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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
Kuan-Jan Lin, Chaung Lin
Nuclear Science and Engineering | Volume 130 | Number 1 | September 1998 | Pages 128-140
Technical Paper | doi.org/10.13182/NSE98-A1995
Articles are hosted by Taylor and Francis Online.
A knowledge-based expert system was developed for generating a pressurized water reactor fuel reload design. First, an initial loading pattern was generated according to the fuel assembly's infinite multiplication factor, by using heuristic rules. Then, the fuel assembly was swapped or rotated, using heuristic rules, to satisfy an assumed search target. The search target was the defined nuclear enthalpy rise hot-channel factor FH at each fuel assembly location. When FH's of a trial loading pattern satisfied the search target, the pattern met the design limit at each exposure checkpoint for all control rods out and D-bank control rods half-inserted conditions, which is the design requirement. The developed program successfully generated several reload cycles for the Maanshan nuclear power plant in Taiwan.