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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Jun Li, Man-Sung Yim, David McNelis
Nuclear Technology | Volume 162 | Number 3 | June 2008 | Pages 293-307
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A3957
Articles are hosted by Taylor and Francis Online.
The development of a fuzzy logic-based barrier (FLB) method for the evaluation of the proliferation resistance of nuclear fuel cycle systems is described in this paper. The method is based on using a group of system-dependent, measurable, or quantifiable variables to define the proliferation barrier effectiveness of a system as fuzzy numbers. The usefulness of the FLB method and the resulting metric in quantifying the proliferation resistance of fuel cycle systems was also investigated by applying it to three fuel cycles, i.e., light water reactor-once-through, light water reactor with mixed oxide fuel, and direct use of spent pressurized water reactor fuel in CANDU reactor. To address the issue of subjectivity in assigning barrier weighting factors or fuzzy numbers, the sensitivity of the results to the definition of fuzzy numbers and weighting schemes was also investigated.