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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
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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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Fusion Science and Technology
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.”
Christos Housiadas, Adolfo Perujo
Fusion Science and Technology | Volume 37 | Number 1 | January 2000 | Pages 68-73
Technical Paper | doi.org/10.13182/FST00-A123
Articles are hosted by Taylor and Francis Online.
The estimation of tritium inventories and permeation fluxes to the coolant in the International Thermonuclear Experimental Reactor (ITER) is an important issue from the safety standpoint. Previous calculations have been performed neglecting ITER's pulse operation because it was assumed that during plasma-off periods the processes become "frozen" until the plasma starts again. It is shown that this assumption may fail in certain cases, particularly in the first wall of ITER, where a larger (by an order of magnitude) inventory and permeation flux to the coolant is obtained when pulse operation is considered. The calculations are performed with the code TMAP4. The discontinuous nature of the plasma operation is mimicked by imposing on the plasma-facing side a heat flux and a particle implantation flux in the form of a quadratic stepwise periodic function oscillating between zero (plasma off) and a maximum value (plasma on).