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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.
Mohamed S. El-Genk, Sung-Ho Kim, Galal M. Zaki, Jeffrey S. Philbin, James F. Schulze, Fabian C. Foushée
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 360-369
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33921
Articles are hosted by Taylor and Francis Online.
To investigate the coolability of a uniformly heated tube by free convection of atmospheric air, heat transfer experiments were conducted using vertical open an-nuli with adiabatic outer walls. To examine the effect of the annulus ratio on the coolability of the heated tube, the experiments employed four annuli (diameter ratios of 1.155, 1.33, 1.63, and 12.0). The operating parameters included heat fluxes up to 1.38 W/cm2 with a corresponding surface temperature of 856K. The results, extrapolated to 1200 K, were used to provide a qualitative estimate of the coolability of multirod bundles, as a function of the equilibrium surface temperature and the pitch-to-diameter (P/D) ratio. Although the decay heat removal rate for P/D values <1.5 increased rapidly with P/D ratio, for larger P/D values the decay heat removal rate was insensitive to either the P/D value or the rod arrangement in the bundle. These results suggest that in TRIGA-type reactors at a typical P/D ratio of 1.12, the maximum decay heat removal level is ∼1 kW/m. This maximum corresponds to an initial decay power following sustained operation at ∼12.5 kW/m.