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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.”
Brent J. Lewis, Aamir Husain
Nuclear Technology | Volume 140 | Number 3 | December 2002 | Pages 279-287
Technical Paper | Radiation Protection | doi.org/10.13182/NT02-A3339
Articles are hosted by Taylor and Francis Online.
A general methodology was developed to estimate geometry factors for internal gamma dose rate calculations within a cylindrical radioactive waste container. In particular, an average geometry factor is needed to calculate the average energy deposition rate within the container for determination of the internal gas generation rate. Such a calculation is required in order to assess the potential for radioactive waste packages to radiolytically generate combustible gases.This work therefore provides a method for estimating the point and average geometry factors for internal dose assessment for a cylindrical geometry. This analysis is compared to other results where it is shown that the classical work of Hine and Brownell do not correspond to the average geometry factors for a cylindrical body but rather to values at the center of its top or bottom end. The current treatment was further developed into a prototype computer code (PC-CAGE) that calculates the geometry factors numerically for a cylindrical body of any size and material, accounting both for gamma absorption and buildup effects.