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
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
Bruce W. Knight, Jr.
Nuclear Science and Engineering | Volume 19 | Number 4 | August 1964 | Pages 393-399
Technical Paper | doi.org/10.13182/NSE64-A18994
Articles are hosted by Taylor and Francis Online.
A tractable mixed numerical-analytic method is given for the approximate design of reflected reactors with cores having simultaneously flat power density, fuel loading, absorber distribution, and moderator distribution. The method as applied to finite cylinders yields a fast digital routine (about 1 sec/calculation on the IBM 704) which gives trustworthy criticality values in systems with important neutron capture at energies above thermal. Corroborative experiments on critical assemblies containing molybdenum and tungsten show power distributions flat to within ±5%.