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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
B. S. Pei, Y. B. Chen, Chunkuan Shih, W. S. Lin
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 134-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33856
Articles are hosted by Taylor and Francis Online.
The performance of five critical heat flux (CHF) correlations with the COBRA IIIC/MIT-1 code was evaluated. These correlations were evaluated against a data group comprised of 2943 axial nonuniform, rod bundle, first-order, and higher rank CHF data points of pressurized water reactor (PWR) core geometries. Among these five CHF correlations, EPRI-1 is the most accurate and has the widest operating ranges. Two kinds of correction factors—cold-wall correction factors and the CHF local quality correction factor—were developed and introduced to EPRI-1 to improve its accuracy in PWR CHF predictions. An in-depth evaluation of the EPRI-1 correlation in the prediction of CHFs of three fuel element abnormalities was also performed. Heat flux spikes and blocked channel conditions have negligible effects on CHFs. For the adverse effects of rod bowing on CHFs, the severity of rod bowing effects depends on the percentage of gap closure between rods, and also on the presence of any thimble tube (cold wall) adjacent to the distorted subchannel. Rod bowing effect parameter correlations under cold-wall conditions were developed. These rod bowing effect parameter correlations were tested; it was proved that they could closely describe the rod bowing effects with no apparent remaining residual trends.