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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 Technology
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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
J. González, P. Zanocco, M. Giménez, M. Schivo, O. Mazzantini, M. Caputo, G. Bedrossian, P. Serrano, A. Vertullo
Nuclear Technology | Volume 171 | Number 1 | July 2010 | Pages 14-26
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A10769
Articles are hosted by Taylor and Francis Online.
This paper presents a model of the Atucha Unit II pressurized heavy water reactor nuclear power plant (currently in the final construction stage) developed in RELAP5/MOD3.3. The nodalization was implemented in order to comply with the probabilistic safety analysis required in the licensing, commissioning, and operating process.The reactor is cooled and moderated by heavy water. Though the primary circuit is equivalent to a two-loop pressurized water reactor, the reactor core consists of vertical channels surrounded by a relatively large volume of heavy water acting as a moderator. This moderator is cooled by an independent system and kept at the same pressure but lower temperature than the primary circuit.The relevant components and systems of the plant are presented and nodalized. The main characteristics of the plant are discussed to achieve a correct representation of the expected physical behavior. Additionally, an integral platform of data management is implemented that processes the geometric and physical data for nodalization and finally generates the code input. Then, a complete tracking of data is possible from the corresponding referenced report to the input deck. This tool facilitates the quality assurance process by independent reviewers. Moreover, the verification of sources and documentation employed can be easily implemented.Initially, the steady state is analyzed by comparing variables obtained with the model with their respective design values and previous calculations performed with other models. Finally, a case of loss of heat sink caused by an electrical supply failure is analyzed. Relevant aspects of the plant dynamic are analyzed and presented for this case. The standard procedure established in the plant to tackle this initiating event is also discussed considering the triggered signals and the configurations of the main systems.