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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.”
Ling Zou, Hongbin Zhang, Jess Gehin, Brendan Kochunas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 535-542
Technical Paper | Fission Reactors / Thermal Hydraulics | doi.org/10.13182/NT13-A19440
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulics (TH)/neutronics/crud multiphysics coupling framework to simulate the crud deposits' impact on crud-induced power shift (CIPS) phenomenon is proposed in this paper. The coupling among three essential physics (i.e., TH, crud, and neutronics) was implemented by coupling the computational fluid dynamics software STAR-CCM+, a newly developed crud module, and the neutronics code DeCART. A typical 3 × 3 pressurized water reactor fuel pin problem was analyzed with this framework and simulation results are presented. Time-dependent results are provided for a 12-month simulation. Simulation results provide the history of crud deposits inventory and their distributions on fuel rods, boron hideout amount inside crud deposits, and power shape changing over time. The obtained results clearly showed the power shape suppression in regions where crud deposits exist, a clear indication of CIPS phenomenon.