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
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Mar 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
S. Sanatani, L. S. Kothari
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 211-217
Technical Paper | doi.org/10.13182/NSE61-A28066
Articles are hosted by Taylor and Francis Online.
To study the diffusion of thermal neutrons in a solid medium, we divide the neutron energy range into two groups, one above and another below the Bragg cutoff energy for the medium. We then apply the method of groups to study the problem. As examples we have considered infinite slabs of beryllium at temperatures of 100°K and 300°K, with an infinite plane source of neutrons at one end of the slab. The flux distributions and the mean neutron energy are calculated for the different cases. It is found that, while for beryllium at 300°K the mean energy is not very much different from the Maxwellian value, for beryllium at T = 100°K results are markedly different from those for a Maxwellian distribution at that temperature. In order to emphasize the effect of the interaction between the two groups in determining the equilibrium flux distributions, we have also made calculation neglecting the interaction and compared these with the earlier results which take account of the interaction.