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 Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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.
R. A. Bennett, R. E. Heineman
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 294-299
Technical Paper | doi.org/10.13182/NSE60-A28859
Articles are hosted by Taylor and Francis Online.
The thermal neutron absorption rate in “1/v” materials has been observed near a discontinuity in the temperature of a graphite moderator. A plausible group diffusion model of the space and energy distributions of the thermal neutrons has been assumed. The experimental data have been used to obtain the transfer cross sections, called rethermalization cross sections, to be used with this model. The cross sections obtained for crystalline graphite are small compared to those expected for gaseous graphite; but they increase by a factor of about seven, from (1.9 ± 0.05) × 10−3 to (14.5 ± 2.6) × 10−3 cm−1, from the lowest temperature of 108°K to the highest temperature of 666°K.
