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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Brent J. Lewis, Dugald B. Duncan, Colin R. Phillips
Nuclear Technology | Volume 77 | Number 3 | June 1987 | Pages 303-312
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33970
Articles are hosted by Taylor and Francis Online.
Data from a reactor operating with a single defective fuel element were used to develop a physically based model for describing the increased release of iodine to the primary coolant following reactor shutdown. Transport of iodine from the fuel-to-sheath gap of the element to the primary coolant is described by a diffusion process. The model has been used to predict the timing of the increased release.