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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.”
Chih-Tien Liu, Hund-Der Yeh
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 322-334
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3420
Articles are hosted by Taylor and Francis Online.
This paper is to study the effects of fracture width on the transport of a radionuclide in a multiple and parallel fractured rock formation. The equation describing the transport of the radionuclide released from the geological repository includes the following mechanisms: advection, dispersion, radioactive decay, and adsorption on the fracture surfaces. The concentration at the inlet of each fracture is assumed constant. An analytical solution was derived based on such a mathematical model by the Laplace transform technique. The solution indicates that identical concentration distributions can be observed in each fracture of the equal-width parallel fractured system. In an unequal-width fractured system, the penetration distances along wide fractures are generally larger than that in a single uniform fractured system. The radionuclide concentration in the wide fracture quickly reaches source concentration in the near-field environment, confirming that the fracture width plays an important role in radionuclide transport through a system of multiple and parallel fractured media.