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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.”
Insoo Jim, Mohamed Abdou
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2159-2168
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30040
Articles are hosted by Taylor and Francis Online.
Activation analysis for the cavity of the PROMETHEUS ICF design, which uses a wetted first wall protection scheme, has been performed. It has been found that the PROMETHEUS cavity produces about 0.9 Ci/W of thermal power at shutdown after the full 30 years operation, which is about the same amount of radioactivity of other ICF and MCF fusion designs with low activation materials. It was possible, however, to reduce the radioactivity inventory level in the shield by one to three orders of magnitude by introducing a new shield design that uses B4C, Pb, SiC and water instead of using the conventional concrete shield. Furthermore, the effect of using the spherical and cylindrical modeling on the prediction of radioactivity in the first wall has been studied. It has been found that the cylindrical model with a point neutron source at the center of the cylinder reduces the radioactivity of the short half-life products to about 80% of the values that would be obtained by using purely spherical modeling. Finally, the 210Po problem associated with the use of lead has been analyzed. It is shown that 210Po produced from neutron interactions with lead is more important than that produced from the bismuth impurity (40ppm) existing in lead if the machine is operated over ∼1 year.