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
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 261-269
Technical Paper | Radiation | doi.org/10.13182/NT76-A31567
Articles are hosted by Taylor and Francis Online.
The properties of energy distributions resulting from transmission of gamma rays through finite cylindrical barriers were studied using a modified version of the MORSE Monte Carlo transport code. Systematic studies were carried out to investigate the effects of density, composition, source energy, and cylinder diameter on the scattered and unscattered flux. In addition the average number of collisions and the contribution of the single-, double-, and triple-scattered photons were calculated for each run. It was found that for the same energy group, the intensity of the scattered flux reaches a maximum at a density that depended directly on the leakage probability but only slightly on composition. The correspondence between the Monte Carlo simulation and experimental results was found to be good.