ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.”
T. Oishi, K. Yamazaki, Y. Hori
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1113-1116
Concept and Facility | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12610
Articles are hosted by Taylor and Francis Online.
To model the fuel supply in nuclear fusion reactors with D-T burning plasmas, the relationship among the D/T fuel ratio, tritium consumption, and reactor output power is analyzed numerically using the TOTAL (toroidal transport analysis linkage) simulation code. In the case that a deuterium-rich pellet is employed, the amount of tritium to be injected to the reactor as the fuel can be reduced compared with the case when the D to T ratio is the same. The fusion output power can be adjusted by controlling the D/T ratio while the electron density is fixed. This control method of the output power by D/T ratio scan can save the tritium consumption compared with that by the density scan, especially in the cases with lower fusion output power.