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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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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.”
R. G. Clemmer, D. K. Sze, P. E. Blackburn, E. VanDeventer, V. A. Maroni
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1612-1618
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29572
Articles are hosted by Taylor and Francis Online.
A 2:1 mixture of LiF and BeF2 (FLIBE), is a potential tritium breeder material for fusion reactors, in particular, the Advanced Safe Pool Immersed Reactor (ASPIRE). A limited experimental campaign was conducted in an effort to test the postulates of the ASPIRE concept: namely, that MoF6 is effective in controlling the tritium species by maintaining the TF form and that MoF6 can serve as a source to plate out Mo on surfaces, thereby making the FLIBE system compatible with the corrosive TF. It was demonstrated experimentally that successive additions of MoF6 achieved quantitative (i.e., greater than 99.7%) conversion of H2 to HF. Thus, MoF6 is effective in controlling the tritium species. The degree of conversion of H2 to HF demonstrates that HF does not attack MO to form H2. This supports the postulate that the system is compatible with Mo. Thus, if it were possible to plate out and maintain a coating of Mo on all surfaces in contact with the FLIBE system, the ASPIRE concept could work. Thermodynamic calculations also confirmed that MoF6 should be capable of quantitatively (>99.9%) converting H2 to HF. There is both experimental and theoretical evidence that a number of MoFx species are present in both the gas phase and the FLIBE solution.