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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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 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. 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.”
E. Uspuras, A. Kaliatka
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 18-25
Technical Paper | Best Estimate Methods | doi.org/10.13182/NT07-A3821
Articles are hosted by Taylor and Francis Online.
This paper evaluates the so-called weak heat conduction mechanism, i.e., the heat transfer from heated-up fuel channels in the radial direction to cooled channels through the adjacent graphite columns in the RBMK-1500 reactor. The influence of this mechanism on the calculation results for a long-term loss-of-coolant accident is investigated.Two possibilities for modeling the heat transfer in the radial direction, between adjacent graphite columns, using the system code RELAP5 are presented: (a) employing the interstructure heat conduction model built into the RELAP5-3D code and (b) employing the model of the reactor gas circuit, which supplies a mixture of gases into the reactor cavity.Both means allow one to predict the localized heatup in the RBMK core. However, the modeling of the reactor gas circuit in parallel with the reactor cooling circuit decreases the calculation time-step size quite significantly. The analysis results demonstrate the capability of the RELAP5-3D code to model heat conduction in the radial direction between different heat structures much more easily and a hundred times faster.