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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.
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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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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.”
H. Y. Khater
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 614-618
Safety and Environment (Poster Session) | doi.org/10.13182/FST98-A11963682
Articles are hosted by Taylor and Francis Online.
Activation and Safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water cooled copper center post and uses a SiC/LiPb blanket. The first wall and shield are made of low activation ferritic steel and cooled with helium. The center post, first wall, inboard shield and blanket were assumed to survive for 2.6 full power years (FPY). On the other hand, the outboard shield and vacuum vessel were assumed to stay in place for 40 FPY. Neutron transmutation of copper resulted in the production of several nickel, cobalt and zinc isotopes. The production of these isotopes resulted an increase of the time-space average resistivity of the center post by about 6% after 2.6 FPY. All of the plant components met the limits for disposal as Class C low level waste (LLW). The off-site doses produced at the onset of an accident are caused by the mobilization of the radioactive inventory present in the plant. Analysis of a Loss of Coolant Accident (LOCA) indicated that the first wall and shield would reach a maximum temperature of less than 700°C during the accident. The calculated temperature profiles and available oxidation-driven volatility experimental data were used to calculate the dose at the site boundary under conservative release conditions. The current design produces an effective whole body early dose of 1.77 mSv at the site boundary.