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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.”
Martin J. R. Pierre, Hugues W. Bonin
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2928
Articles are hosted by Taylor and Francis Online.
The availability of the Monte Carlo-based code MCNP 4A has made possible the simulation of the low-enriched uranium (LEU)-fueled SLOWPOKE-2 reactor using a probabilistic approach. The reactor core and its surrounding pool can be modeled in three dimensions with numerous details included in the representation. Significant improvement from previous modeling attempts was obtained with the MCNP 4A simulation, with the discrepancy between the calculated and experimental values of the excess reactivity at 20°C reduced to only 0.2 mk. The analysis suggests the error of the MCNP 4A-calculated excess reactivity as between 1 and 2 mk.The SLOWPOKE-2 reactor was then simulated with its single control rod at various degrees of insertion in the core: The reactivity worth of the rod was calculated as 7.85 mk, only 2.4 mk above the measured value. MCNP was then used for predicting the temperature effects on the excess reactivity. Although the inherent safety of the SLOWPOKE-2 reactor was confirmed in the simulation, the temperature dependence of the excess reactivity could not however be accurately predicted, due for the most part to the lack of appropriate cross-section libraries available at the time of this work. The potential of MCNP 4A is nevertheless clearly demonstrated for the simulation of the LEU-fueled SLOWPOKE-2 reactor, once the missing cross sections become available for the low temperatures at which the reactor operates.