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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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 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. 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.”
A. Robinson, L. El-Guebaly, D. Henderson
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 715-719
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12469
Articles are hosted by Taylor and Francis Online.
Currently, there is an ongoing international effort to develop and characterize W alloys that are suitable for fusion applications. In this report, five key W alloys were examined for the advanced divertor design of ARIES-ACT - the latest ARIES tokamak design. The most promising alloys appear to be W-1.1TiC and W-La2O3. At the end of the divertor lifetime (~4 years), the maintenance dose of these alloys very closely matches those of W with nominal impurities. Unfortunately, even with pure W, the divertor is not clearable, which indicates that it must be recycled or disposed of in a geological repository. The radiation damage and transmutation are expected to degrade the physical properties of any material. The radiation damage level in W is low compared to ferritic steel - a remarkable feature for tungsten. For ARIES-ACT operating conditions, transmutation of W does not appear to present a significant issue.