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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.”
Sol-Il Su, Man-Sung Yim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 71-88
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3078
Articles are hosted by Taylor and Francis Online.
Ion-exchange resins represent one of the most important waste streams in low-level waste management due to the unstabilized nature of the waste form and the large amount of radioactivity contained. To describe the release of radionuclides from ion-exchange resins stored in a disposal facility, a mechanistic release model was developed. The model is based on description of radionuclide migration both in the resin bead phase and the bulk pore water phase within waste containers. This modeling setup provides the capability to describe all the major physical processes taking place for the release of radionuclides. Because of the difficulty in obtaining analytical solutions, the numerical solution approach was employed in this model.The new resin release model was used to examine key processes and parameters in describing radionuclide release. These were found to be diffusion within the bulk pore water phase, flow rate of infiltrating leachant water, concentration of counterions of the leachant water, and sorption during the transport in the bulk pore water phase. Some parameters were found to have little impact in describing the release. These include the interdiffusion coefficient within resin beads and the density and radius of resin beads. Existing simplified modeling approaches were also compared with the new resin release model, and validities of using these simplified models are discussed.