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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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.”
F. Andritsos, M. Zucchetti
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 973-977
Tritium Technology, Safety, Environment, and Remote Maintenance | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40280
Articles are hosted by Taylor and Francis Online.
In a fusion reactor, the neutron flux will cause activation of the plasma chamber. The volumetric decay heat associated with this activation is removed, during normal operation, by forced flow cooling circuits. Its effects under post accidental conditions are a matter of concern since they can cause temperatures higher than allowed leading to the degradation of the properties and even structural failure of all or some of the reactor components. Here, an overview of the post accidental temperature transients, performed under the European Fusion Program for a variety of tokamak devices, is presented. The modelling activities, including the neutronic, activation and thermal part, are described. The latest results concerning the SEAFP reactor study are given. Generally, the most dangerous temperature peak happens long after the accident (typically 1 – 2 months) thus allowing for a considerable margin for intervention. Appropriate design of the region outwards from the vacuum vessel can provide the necessary thermal links so as not to compromise the structural stability of the containment even in the envelope conditions of complete and permanent loss of every form of active cooling.