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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Winter Conference and Expo
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Orlando, FL|Renaissance Orlando at SeaWorld
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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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SRS partnership’s mission is to dissolve spent fuel
A collaboration between Savannah River Nuclear Solutions (SRNS) and Savannah River National Laboratory (SRNL) is making progress toward processing non-aluminum spent nuclear fuel (NASNF) as part of the site’s accelerated basin de-inventory mission. SRNL is the managing and operating contractor at the Department of Energy’s Savannah River Site in South Carolina.
A. D. Vaughn, R. I. Smith
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 146-152
Technical Paper | Fuel Cycle | doi.org/10.13182/NT72-A31129
Articles are hosted by Taylor and Francis Online.
The plutonium concentrations in mixed-oxide fuel rods containing distinct sizes of particulate plutonium oxide have been determined using high resolution gamma-ray spectrometry. The fuel rod enrichments were in the range 2 to 2.5 wt% in natural UO2. Individual rod enrichments were determined to within ±0.1 wt% by comparison with a known standard. Differences in plutonium iso-topic composition were discemable also, in addition to the differences in plutonium enrichment. The technique provides an inexpensive nondestructive method of determining in situ plutonium composition and content of assembled fuel rods, for purposes of quality assurance and accountability control.