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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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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.
T. C. Wiencek, R. F. Domagala, H. R. Thresh
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 608-616
Technical Paper | Material | doi.org/10.13182/NT85-A33683
Articles are hosted by Taylor and Francis Online.
Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400°C for up to 1981 h. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No tested modification of a standard fuel plate showed any significant reduction in plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (a) the reaction of the uranium silicide with aluminum to form U(AlSi)3 and (b) the release of hydrogen and subsequent creep and pillowing of the fuel plate.