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
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
G. D. Joanou, J. R. Triplett, R. M. Wagner
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 363-369
Technical Paper | doi.org/10.13182/NSE64-A20056
Articles are hosted by Taylor and Francis Online.
An iterative approach to the reactor burnup problem is developed on the basis of analytical solutions for the variable-coefficient burnup equations. The time dependence of the depletion matrices, A(t), is approximated by a polynomial representation. The number of basic time points for which spatial-diffusion calculations during burnup are required is determined only by the order of approximation necessary to give a reasonably good fit for the time dependence of A(t). Usually a low-order approximation is sufficient, so the number of diffusion calculations is reduced to a minimum. The method is applicable both to survey-type calculations and to detailed reactor-burnup studies. A comparison of some results obtained with the method described in this paper and with standard calculational methods is given for a typical example. The results show the rapid convergence and accuracy of the proposed procedure.