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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
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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.
D. N. Sah, C. S. Viswanadham, Sunil Kumar, P. R. Roy
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 136-146
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34236
Articles are hosted by Taylor and Francis Online.
Samples of Zircaloy-2 cladding from four UO2 fuel elements irradiated in the Tarapur Atomic Power Station boiling water reactor up to fuel burnup levels of 9599 to 12 627 MWd/tonne U are examined using scanning electron microscopy and electron probe microanalysis to study the nature of deposits formed on the inner surface of the cladding. The clad samples from one fuel element that was located nearest to the control blade and had a fission gas release of 3.7% have deposits on the surface. Uranium, zirconium, cesium, oxygen, tellurium, barium, tin, and rubidium are present in the deposit. The deposit is composed of two layers: a layer toward the fuel, containing mainly uranium, cesium, and oxygen, and another toward the cladding, containing uranium, zirconium, cesium, and oxygen. The formation of the deposits is explained by a localized high release of volatile fission products from the fuel and their migration to the clad surface.
