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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.”
Woan Hwang, Cheol Nam, Thak Sang Byun, Young Cheol Kim
Nuclear Technology | Volume 123 | Number 2 | August 1998 | Pages 130-141
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2887
Articles are hosted by Taylor and Francis Online.
Computational models for analyzing in-reactor behavior of metallic fuel pins in liquid-metal reactors under steady-state conditions are developed and implemented in the Metal fuel performance Analysis (computer) Code for Simulating the In-reactor behavior under Steady-state conditions (MACSIS). Sodium logging and constituent redistribution effects are considered in calculating the temperature profile. The model for the radial redistribution of the fuel constituent is based on the thermotransport theory. The fission gas release model takes multibubble size distribution into account to characterize the lenticular bubble shape and the saturation condition on the grain boundary. Finally, the clad strains are calculated from the amount of fission gas released and interface pressure. Sample calculations are performed to verify each model. The results show that in general, the predictions of MACSIS agree well with the available irradiation data.