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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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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.”
Y. Maeda, Y. Edao, S. Yamaguchi, S. Fukada
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 131-134
Technical Paper | Blanket Design | doi.org/10.13182/FST54-131
Articles are hosted by Taylor and Francis Online.
The diffusion, solution and permeation coefficients of hydrogen isotopes in liquid Li-Pb which is a candidate liquid blanket material for fusion reactors were determined in the temperature range 573-973K using an unsteady permeation method. Each coefficiens was correlated to temperature as follows:DLi-Pb = 1.8 × 10-8 exp(-11590/RT) [m2/s] (1)KLi-Pb = 2.1 × 10-6 exp(-18700/RT) [1/Pa0.5] (2)PLi-Pb = 1.8 × 10-9 exp(-30290/RT) [mol/msPa0.5] (3)The hydrogen permeation flux depends on the square root of pressure at 773-973K. Although the power of pressure declined below 0.4 when temperature was below 673K, the effects of surface resistance were neglected above 673K.The hydrogen solubility in liquid Li-Pbwas found to correlate with a Sievert's constant.We calculated a height-equivalent to theoretical-plate of a gas-liquid countercurrent extraction tower for tritium recovery rates in liquid Li-Pb to beHL = 7.0 × 10-2 [m] (4)