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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Aarno Isotalo
Nuclear Science and Engineering | Volume 180 | Number 3 | July 2015 | Pages 286-300
Technical Paper | doi.org/10.13182/NSE14-92
Articles are hosted by Taylor and Francis Online.
Four schemes for coupling the neutronics and depletion in burnup calculations are compared in four assembly segment test cases with various step lengths. Three of the coupling schemes use only one transport solution per step. While none of the methods was superior in every test case or in every respect, there are significant differences that can make one or the other preferable in different applications. The fourth method included in the comparison is the one dubbed CE/CM in our previous study, which compares schemes that use two transport solutions per step. The methods using only one transport solution per step were found to be more accurate than CE/CM but less accurate than the newer LE/LI and LE/QI methods. In cases where desired output intervals, rather than accuracy, are the limiting factor for step lengths, methods using only one transport solution per step can still provide a major advantage even when compared to LE/LI and LE/QI. Significant differences were also observed in the propagation of the statistical uncertainty from Monte Carlo neutronics through the different methods. While this topic was not studied further, it seems that differences in error propagation may in some cases be as significant as those in accuracy.