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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Y. Y. Chang, S. K. Loyalka
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 235-250
Technical Note | doi.org/10.13182/NSE81-A21357
Articles are hosted by Taylor and Francis Online.
A computer code TWOLASER has been developed for neutronic calculations of square lattice cells in nuclear power reactors. The computer code, which uses new methods for solutions of the integral transport equation and burnup equations, has been used to assess the accuracy and speed of the LASER code. The new code considers actual two-dimensional geometry of the cell as compared to the one-dimensional approximation used by LASER. Calculations have been performed on a sample problem for a burnup of 10.6 MWd/kg fissile. Results from these calculations show that the one-dimensional approximation used by LASER is good for the sample problem. However, the method used by LASER for the solution of burnup equations is not efficient. A modified version, MLASER, of the LASER code has also been developed in this research. This version uses the one-dimensional approximation of LASER and the new method for the solution of burnup equations, and it also provides good results as compared to the results given by the two-dimensional code. However, for the same accuracy, MLASER is computationally much faster (a factor of 4) than the original LASER program. The code TWOLASER can be used to provide data for benchmarking, and MLASER can be used for the replacement of the original LASER.