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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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.
J. P. Nichols, E. D. Arnold, D. K. Trubey
Nuclear Science and Engineering | Volume 17 | Number 3 | November 1963 | Pages 486-491
Technical Paper | doi.org/10.13182/NSE63-A17403
Articles are hosted by Taylor and Francis Online.
The shielding and containment criteria for the Transuranium Processing Plant obtained by calculations and experiments are given. The shield evaluation studies (for cell walls, cell windows, and fission source carriers) utilized experiments at the ORNL Lid Tank Shielding Facility and IBM-7090 computer calculations for determination of neutron transport, neutron activation, and gamma penetration. These studies also included an evaluation of the effects of credible accidents occurring in the facility.
