ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
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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.
C. E. Winters
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE63-A17396
Articles are hosted by Taylor and Francis Online.
The High Flux Isotope Reactor (HFIR), now being constructed at Oak Ridge National Laboratory, was designed for almost the single purpose of transmuting elements at the highest possible rate consistent with reasonable extrapolations of proven technology. The reactor is of the fluxtrap type, with a cylindrical core. It is light-water cooled and beryllium reflected. At the design power of 100 Mw the reactor will produce a calculated unperturbed neutron flux of 5 × 1015 neutrons/cm2, sec in the target region. A target of 300 gm of Pu242 for the production of transplutonium elements will reduce this flux to 2 or 3 × 1015.