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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.
Saleem A. Ansari, Syed Khwaja Ayazuddin
Nuclear Technology | Volume 67 | Number 1 | October 1984 | Pages 9-13
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33524
Articles are hosted by Taylor and Francis Online.
Reactor noise measurements at Pakistan Research Reactor were analyzed for the magnitude and frequency spectrum of the fluctuation of neutron density. The measurements were aimed at determining the effect of (a) the magnitude of reactor power, (b) coolant flow rate, and (c) position of control rods on the fluctuation of reactor power. Two peaks in the power spectral density of neutron noise are explained to be due to control rod vibration. A one-dimensional thermal-hydraulic model of the reactor core was also developed to explain the remaining noise spectra on the basis of coolant temperature fluctuation.
