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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.”
Heimo Bürbaumer, Gerald Kamelander
Fusion Science and Technology | Volume 37 | Number 2 | March 2000 | Pages 131-145
Technical Paper | doi.org/10.13182/FST00-A129
Articles are hosted by Taylor and Francis Online.
The temporal evolution of the operating point of a fusion plasma during the ignition access, during ignited and subignited operation phases, is analyzed for plasmas like that of the International Thermonuclear Experimental Reactor (ITER) on the basis of a one-half-dimensional set of equations including feedback equations for auxiliary heating and fuel supply. It is shown that simple proportional feedback controls do not work taking into account the delay times in the control process. Proportional-integral-differential (PID) and improved types of control are examined for the purpose of controlling a fusion plasma against sudden parameter changes. On this basis a study on the simultaneous use of D-T fuel injection and auxiliary heating control methods for an ITER-like plasma is carried out, resulting in an algorithm capable of finding the optimal operation point in the ignited regime or a high-Q operating point in a subignited case taking into account density and beta limits and stabilizing the reactor performance against changes in confinement.