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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
2024 ANS Annual Conference
June 9–12, 2024
Las Vegas, NV|The Mirage
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NRC seeks comments on new fee schedule for FY 2024
The Nuclear Regulatory Commission is asking for feedback on proposed changes to the annual, licensing, inspection, and special projects fees for fiscal year 2024.
The proposed fee rule, published February 20 in the Federal Register, is based on the FY 2024 Congressional Budget Justification as a full-year appropriation, but it has not yet been enacted. The final rule will be based on the NRC’s actual appropriation, and the agency will update the final fee schedule as appropriate.
David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr.
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 82-93
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33597
Articles are hosted by Taylor and Francis Online.
Dispersed-flow film boiling data were obtained in a large rod bundle (8 × 8) under steady-state and transient conditions with upward flowing high-pressure, high-temperature water. The bundle is equipped with detailed thermometry, and has geometry typical of later generation pressurized water reactors with 17 × 17 fuel assemblies. Comparisons with the data to empirical correlations commonly used to predict heat transfer in dispersed flow indicate that the Dougall-Rohsenow and Groeneveld-Delorme correlations overpredict and underpredict heat transfer, respectively, while the Groeneveld 5.7 and Condie-Bengston IV correlations perform reasonably well. Spacer grids are shown to cause rod surface temperature depressions of up to 100 K from the upstream to downstream side of the grid. Grid effects persist for 20 to 30 hydraulic diameters downstream of the grid.