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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.”
Chikara Konno, Satoshi Sato, Kentaro Ochiai, Masayuki Wada, Seiki Ohnishi, Kosuke Takakura, Hiromasa Iida
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 743-746
Heavy Ion Transport | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Protection | doi.org/10.13182/NT09-A9299
Articles are hosted by Taylor and Francis Online.
The three-dimensional Sn code Attila of Transpire, Inc., can use computer-aided-design data as direct geometrical input and can deal with assemblies of complicated geometry without much effort. The International Thermonuclear Experimental Reactor (ITER) organization plans to adopt this code as one of the standard codes for nuclear analyses. However, validation of calculations with this code has not been carried out in detail so far. Thus, we validate this code through analyses of some bulk experiments and streaming experiments with deuterium-tritium neutrons at the Japan Atomic Energy Agency Fusion Neutronics Source. Analyses with the Sn code system DOORS and Monte Carlo code MCNP4C were also carried out for comparison. The agreement between the Attila and DOORS calculations is very good for the bulk experiments. For the streaming experiments Attila requires special treatment (biased angular quadrature sets or last collided source calculation) as well as DOORS in order to obtain similar results as those with MCNP, though Attila consumes much more time than DOORS.