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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.
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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
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.
J. Tommasi, E. Dupont, P. Marimbeau
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 119-133
Technical Paper | doi.org/10.13182/NSE154-119
Articles are hosted by Taylor and Francis Online.
The PROFIL and PROFIL-2 experiments performed in the Phénix demonstration fast reactor irradiated 130 small separate samples containing almost pure isotopes. These highly accurate experiments are a very specific and powerful source of information on the nuclear data of major and minor actinides and several fission products. Their analysis was carried out using the ERANOS-2.0 code system associated to JEFF-3.0 cross-section data, UKFY3.5 fission yield data, and JEF-2.2 decay data. The consistency of the results demonstrates the overall good quality of the actinide nuclear data and experimental techniques used and points out where specific improvement is necessary: fission yields of 235U on neodymium isotopes; integral capture cross sections of 232Th, 233U, 241Pu, 242Pu, and 241Am (and to a lesser extent, 240Pu and 237Np); and branching ratios for 241Am capture. A similar analysis characterizes the degree of accuracy of the integral capture cross sections of 19 fission products. Future plans include the analysis of two new experiments of the same kind, included in the current Phénix experimental program, and the use of a consistent set (cross sections, fission yields, and decay data) of the latest JEFF-3.1 nuclear data files.