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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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 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.”
Ryan Hunt, Hongjie Zhang, Alice Ying, Michael Ulrickson
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 354-358
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12379
Articles are hosted by Taylor and Francis Online.
This research reveals the results of a thermo-mechanical stress analysis of the beryllium and CuCrZr components of the Enhanced Heat Flux (EHF) First Wall (FW). Under the EHF thermal load, differential thermal expansion at the Be/CuCrZr interface can potentially lead to failure of the beryllium tiles. We have shown that the stress profile in both beryllium and CuCrZr can be improved by reducing the dimensions of the beryllium tiles covering the FW panels.In addition, our research investigated a failure condition for the FW finger's design. Specifically, we assessed the temperature profile at the CuCrZr/water interface of the EHF FW finger in the event of a single failed tile. This was done in order to determine whether or not the critical heat flux condition occurs in the coolant channel after a single tile failure. Assuming the failure of a single tile between 11.75mm and 50mm in size, temperature profiles were generated assuming flat, rectangular water cooling channels. It was found that tile failure from the edges of the finger resulted in considerably higher temperatures than tile failures at the middle of the finger. Failure of a tile along the edge of the finger may cause catastrophic failure, as the critical heat flux condition occurred at the CuCrZr/water interface even for tiles as small as 11.75mm in size.