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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.”
James L. Conca, Michael J. Apted, Wei Zhou, Randolph C. Arthur, John H. Kessler
Nuclear Technology | Volume 124 | Number 1 | October 1998 | Pages 88-100
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2911
Articles are hosted by Taylor and Francis Online.
A flow barrier system (FBS) that includes a Richards barrier acts in an unsaturated hydrogeologic system to prevent the advective flow of water down through the barrier. Thus, an FBS placed above any solid waste material buried in the unsaturated zone could greatly aid in isolating the waste by keeping the waste away from flowing water. The FBS, consisting of a layer of highly conductive, fine-grained material overlying a sloped gravel layer, is proposed to isolate high-level radioactive waste (HLW) at a candidate disposal facility located in the unsaturated zone at Yucca Mountain in Nevada. A series of laboratory experiments were conducted to (a) assure that the FBS of a specific design can divert the anticipated maximum advective flow (under ideal conditions as well as for the case of a disturbed interface between the two layers caused by, for example, improper initial emplacement or faulting due to seismic activity), (b) investigate water imbibition into the gravel, and (c) measure the diffusion coefficient of the tuff gravel under partially saturated conditions. The main results show that (a) the FBS used in the study can divert point- source flow rates as high as 2.6 × 105 l/yr; (b) this FBS will continue performing with offsets of the interface as great as 50 cm or more; (c) after 12 months of testing, moisture penetrates the gravel only several grain diameters; and (d) the gravel effective diffusion coefficient is <10-11 cm2/s under such low partial saturations. These results indicate that a properly designed FBS can be successful at isolating the HLW under the anticipated range of environmental conditions that exist both now and in the future at Yucca Mountain.