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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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January 2025
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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Hans-Werner Wiese
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 68-80
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34803
Articles are hosted by Taylor and Francis Online.
Based on the use of the Joint Evaluated File (JEF-1) with the KARBUS burnup code system and subsequent KORIGEN code calculations, the characteristics of spent pressurized water reactor mixed-oxide (MOX) fuels are analyzed. Actinide masses, decay heat, radioactivities, and radiation are discussed for burnups of 40 to 55 GWd/tonne HM for MOX fuels based on natural uranium and on uranium tailings. Multiple plutonium recycling is considered at a burnup of 50 GWd/tonne HM. The results are compared with earlier data at a burnup of 33 GWd/tonne HM. The high-exposure MOX fuels are found to contain large amounts of the heat-releasing and radiating nuclides, 238Pu and 244Cm. The 238Pu in the plutonium, which is to be used for the fabrication of fuel elements from recycled MOX, requires special shielding or a change from glove box techniques to an automated treatment.
