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Division Spotlight
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.
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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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.”
Mark A. Tries, Leo M. Bobek
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 319-323
Technical Note | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3481
Articles are hosted by Taylor and Francis Online.
A method is presented for the determination of the leakage rate for containment vessels of water-cooled reactors. The method is applicable to Type A tests for which the containment vessel is pressurized to some initial overpressure, and subsequent measurements of absolute air pressure and temperature are made to determine the leakage rate. The proposed method incorporates the desirable features of the recommended method for the determination of the leakage rate, namely, that the measured data all have equal statistical weight, the leakage rate is not estimated using finite differences, and the leakage rate is normalized to the initial air content in the containment vessel. The major assumptions of the proposed method are incompressible airflow and a constant absolute air temperature. The proposed method is based on a reasonably accurate description of absolute dry air pressure over time, for which parameters are obtained using a linear regression technique on the transformed pressure measurements. Under the given assumptions the transformed pressure measurements are linear, and therefore, the proposed method avoids the drawback that is encountered in the recommended method of applying a linear model to nonlinear data. The pressure function then is used to determine the leakage rate as a function of time and the integral leakage rate for the duration of the test. Also, the method is readily adaptable to scaling the integral leakage rate to different initial air pressures in the containment vessel. In addition, the assumption of an incompressible airflow is considered to be reasonable for initial Mach numbers less than or equal to 0.4.