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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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
Fusion Science and Technology
American Nuclear Society supports IAEA’s condemnation of attack on Ukraine nuclear power plant
Statement from American Nuclear Society President Steven Arndt and Executive Director and CEO Craig Piercy:
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 | dx.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.