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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
TVA files for Clinch River SMR construction permit
The Tennessee Valley Authority announced yesterday that it has submitted a construction permit application to the Nuclear Regulatory Commission for the construction of a GE Vernova Hitachi Nuclear Energy BWRX-300 small modular reactor at the Clinch River nuclear site in Oak Ridge, Tenn.
Yuh-Ming Ferng, Yin-Pang Ma, Jer-Cherng Kang
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 186-196
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3237
Articles are hosted by Taylor and Francis Online.
Multidimensional thermal-hydraulic characteristics in the secondary side of a steam generator (SG) are simulated by way of flow-boiling models. These models essentially belong to the so-called first-principle models that are derived from the conservation laws. The calculated results can provide the whole picture of thermal-hydraulic phenomena and the localized distributions of velocity, pressure, enthalpy, and void fraction, etc. in the secondary side of the SG. In addition, with the help of these localized flow characteristics, the forcing sources can be estimated for predicting flow-induced vibration (FIV) damage suspected in the tube bundles around the U-bend region. These calculated results can provide important information to help the FIV prediction for SG U-tubes and to find where the most possible FIV damage is located.