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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.
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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.”
Yasuteru Sibamoto, Hideo Nakamura, Yoshinari Anoda
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 119-132
Technical Paper | Radioisotopes | doi.org/10.13182/NT01-A3163
Articles are hosted by Taylor and Francis Online.
Neutron radiography was used to observe the behavior of molten lead-bismuth alloy injected into a thin (10-mm) semicircular vessel, which was empty or contained saturated water. The fluid velocity distribution for the melt injected into the empty vessel was successfully measured using particle image velocimetry (PIV). The numerical analysis for this case using the FLOW-3D code revealed that the wall heat transfer attenuates the rotational speed of swirls that were formed during the melt injection. The melt-coolant interaction experiment demonstrated several features of molten fuel and coolant interactions in the reactor pressure vessel lower head. The violent vapor expansion occurred at the initial melt impact on the saturated pool water. A one-dimensional model predicted the observed behavior well by assuming the adiabatic expansion immediately after an instantaneous heat transfer during the first melt coolant contact. A crust was formed between the melt and coolant by the heterogeneous distribution of the coolant and pool melt. The convective velocity distribution in the pool melt was measured well by the PIV.