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.
Donald R. Green
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 271-275
Technical Paper | doi.org/10.13182/NSE62-A26067
Articles are hosted by Taylor and Francis Online.
An instrument for nondestructively mapping core to cladding heat transfer quality in nuclear fuel elements has been developed. Heat transfer defects down to in. diameter in Zircaloy-2 clad and down to in. diameter in X-8001 aluminum alloy clad uranium fuel elements have been detected. An infrared radiometer was used to detect fuel element surface temperature variations during induction or plasma arc jet heating. The unusual application of plasma arc heating in this instrument made heat transfer testing of nonuniform fuel elements feasible.