ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
F. S. Gunnerson, D. T. Sparks, D. K. Kerwin
Nuclear Technology | Volume 52 | Number 1 | January 1981 | Pages 86-99
Technical Paper | Fuel | doi.org/10.13182/NT81-A32692
Articles are hosted by Taylor and Francis Online.
An in-pile power-cooling-mismatch (PCM) test designed to investigate the behavior of a nine-rod PWR-type fuel bundle under intermittent and sustained periods of high temperature film boiling operation was recently conducted. Emphasis was placed on departure from nucleate boiling (DNB) and return to nucleate boiling (RNB), rod-to-rod interactions, and fuel rod failure. Results indicate that power-coolant variations induced DNB and RNB within the nine-rod test bundle in an irregular, nonsymmetric fashion. Direct rod-to-rod DNB, RNB, and fuel rod failure propagation were not observed. However, a single rod-to-rod interaction was suspected, that being RNB of one rod abetting the onset of DNB on an adjacent rod. This interaction was possibly due to hydraulic coupling. The power and inlet coolant conditions at the onset of DNB on the center fuel rod were indistinguishable from previously obtained PCM data for separately shrouded test rods; thus, the single-rod data base may be applicable for assessing the onset of DNB conditions of an interior fuel rod within a small cluster.