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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
H. D. Brown
Nuclear Science and Engineering | Volume 2 | Number 5 | September 1957 | Pages 687-693
Technical Paper | doi.org/10.13182/NSE57-A25436
Articles are hosted by Taylor and Francis Online.
The solution of the equations describing the reactor state is obtained by numerical integration of the differential equations on an IBM-650. The general description includes the dependence of lattice constants and absorption cross sections upon the temperatures of various components and accommodates the effects of manipulations of the geometric buckling and of the total absorption cross section. The reactor kinetic equations are put into difference form suitable for numerical solution. Measures are described for eliminating divergences introduced by the numerical treatment of the coupling among temperature coefficients, delayed neutrons, and flux.