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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.”
X. Cheng
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 52-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3717
Articles are hosted by Taylor and Francis Online.
In the frame of the European PDS-XADS (Preliminary Design Study-EXperimental Accelerator-Driven System) project, two concepts of a subcritical reactor core cooled by liquid lead-bismuth eutectic (LBE) were proposed. In this paper, the local thermal-hydraulic behavior of both LBE-cooled reactor-core concepts was analyzed. For this purpose, the MATRA subchannel analysis code (Multichannel Analyzer for Steady States and Transients in Rod Arrays) was selected, and modification was made for its applications to XADS conditions. Compared to the small-core concept, the large-core concept has a much lower hydraulic resistance, lower local coolant velocity, and lower temperatures of coolant and fuel pins. This enables the natural convection approach for removing reactor heat and for short-term realization of the core design using available technologies. The fuel assembly of the small-core concept has a tight configuration that leads to a high flow velocity and high pressure drop. The high power density of the small core results in high local temperatures of coolant, cladding, and fuel. Both coolant velocity and cladding temperature are such that special attention has to be paid to avoid corrosion and erosion damage of cladding materials. A parametric study shows that under the parameters considered, the mixing coefficient has the biggest effect on the coolant temperature distribution, whereas the cladding temperature is strongly affected by the selection of heat transfer correlations.