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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
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.
