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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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Nuclear Science and Engineering
March 2025
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February 2025
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.
Koichi Okuno, Hideaki Matsue, Satoru Miyata, Yoshiaki Kiyanagi
Nuclear Science and Engineering | Volume 173 | Number 2 | February 2013 | Pages 139-149
Technical Paper | doi.org/10.13182/NSE12-15
Articles are hosted by Taylor and Francis Online.
Trace element analysis using instrumental neutron activation analysis for neutron shield concrete made from colemanite and peridotite rocks is carried out. Also, an activation estimation for the concrete wall in the accelerator neutron source facility is calculated using the obtained element data. The results show that the amount of short-half-life nuclide production in the neutron shield concrete is ˜1/100 that of limestone concrete and also that the amount of 60Co production is 1/5 to 1/8 that of limestone concrete. From these results, the activation property of the neutron shield concrete was found to be much less than that of the limestone concrete, which has been previously reported as having low activation.