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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.”
Rainer Moormann, Werner Schenk, Karl Verfondern
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 183-193
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3215
Articles are hosted by Taylor and Francis Online.
The stringent safety demands for advanced small pebble bed high-temperature reactors (HTRs) are outlined. Main results of German studies on source term estimation are discussed. Core heatup events are no longer dominant for modern fuel, but fission product transport during water ingress accidents (steam cycle plants) and He-circuit depressurizations are relevant, mainly due to remobilization of fission products that were plated out in the course of normal operation or that became dust borne. The following important lack of knowledge was identified: Data on plateout in normal operation are insufficient, as are data on behavior of dust-borne activity in total; better knowledge in these fields is also important for maintenance/repair and design/shielding. For core heatup events, the influence of burnup on temperature-induced fission product release has to be measured for future Pu-containing high burnup fuel; furthermore, transport mechanisms out of the He circuit into the environment require further examination. For water/steam ingress events, mobilization of plated-out fission products by steam or water has to be considered in detail along with steam interaction with kernels of particles with defective coatings. For source terms of depressurization, a more detailed knowledge of flow pattern and shear forces on surfaces is necessary. To improve the knowledge on plateout and dust in normal operation and to generate specimens for experimental remobilization studies, planning/design of plateout/dust examination facilities to be added to HTRs running in the next future reactors [HTR10 and the High-Temperature Engineering Test Reactor (HTTR)] is proposed. For severe air ingress and reactivity accidents, which belong to hypothetical events with frequencies <1 × 10-7 yr-1, behavior of future advanced fuel elements has to be experimentally tested.