ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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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.
J. E. Hench, D. J. Liffengren
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 544-550
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30851
Articles are hosted by Taylor and Francis Online.
The experimental results of fuel rod failure on the heat transfer effectiveness of spray cooling a Zircaloy-clad simulated BWR fuel bundle were evaluated from the design engineer viewpoint to determine the adequacy of the emergency core cooling system (ECCS) design. The overall results of the full-size 49-rod Zircaloy-clad internally pressurized bundle indicate that the ballooning and perforation associated with cladding failure did not significantly change the heat transfer effectiveness (i.e., peak cladding temperatures) of the ECCS spray cooling mode. Furthermore, the distortion was local in nature so the flow area reduction would not affect the ability of the ECCS flooding mode to accomplish the design objectives.