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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.”
Bradley J. Micklich, Franz X. Gallmeier, Michael Wohlmuther
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 700-705
Accelerators | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Accelerators | doi.org/10.13182/NT09-A9293
Articles are hosted by Taylor and Francis Online.
Component radioactivation is an important problem in accelerator facilities, impacting operations, maintenance, decommissioning, and disposal. Radionuclide inventories are calculated for an 8-cm-diam, 30.9-cm-long lead target irradiated by 660-MeV protons using the particle transport code MCNPX and the transmutation codes CINDER'90, ORIHET-3, and SP-FISPACT. The results using the various codes and data libraries are compared with experimental measurements. Comparisons are also made between the outputs of the three codes for nuclides not represented in the measurements. For more than half the nuclides studied, the codes agree with the measurements within a factor of 2, and nearly all agree within a factor of 10. The present set of codes and nuclear data files are largely adequate for calculating radioactivation in accelerator facilities, but there is room for substantial improvement for selected radionuclides.