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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
Chonghai Cai, Kai Xu, Haixia An, Haicheng Wu
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 304-317
Technical Note | doi.org/10.13182/NSE08-62TN
Articles are hosted by Taylor and Francis Online.
Complete sets of neutron nuclear data, including all kinds of cross sections, angular distributions of elastic scattering, energy spectra and/or double-differential cross sections of all emitted particles, and gamma production data (production cross sections and multiplicity, angular distributions, and energy spectra) in all kinds of reactions for n + 63Cu and n + 65Cu below 20 MeV are calculated and evaluated. The calculated or evaluated cross sections are in good accordance with the experimental values for those reactions with experimental data. Particularly for the neutron leakage current in the benchmark Oktavian and the effective multiplication factors in six benchmark assemblies, our calculated values are in much better agreement with experimental data than those of several existing evaluation files.