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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 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.”
Chikara Konno, Yukio Oyama, Fujio Maekawa, Yujiro Ikeda, Kazuaki Kosako, Hiroshi Maekawa, Mohamed A. Abdou, Edgar F. Bennett, Anil Kumar, Mahmoud Z. Youssef
Fusion Science and Technology | Volume 28 | Number 2 | September 1995 | Pages 347-365
Technical Paper | Fusion Neutronics Integral Experiments — Part II / Blanket Engineering | doi.org/10.13182/FST95-A30650
Articles are hosted by Taylor and Francis Online.
Neutronics experiments on annular blanket systems that use a pseudoline source are performed. The shape of the annular blanket system is a rectangular parallelepiped (1300 × 1300 mm2 and 2040 mm long) with an inner cavity of 425.5 × 425.5 mm2 and 2040 mm long. The annular blanket consists of a 15-mm-thick first wall (Type 304 stainless steel) and 406-mm-thick breeder zone (inner lithium oxide and outer lithium carbonate). Deuterium-tritium neutron sources are set at the center of the inner cavity of the annular blanket system, and the pseudoline source is obtained by oscillating the annular blanket system back and forth in a 2-m span. Three annular blanket configurations are examined: the reference blanket, a blanket covered with 25-mm-thick graphite armor, and an armor blanket with a large opening (376 × 425.5 mm). The neutronics parameters of tritium production rate, neutron spectrum, and activation reaction rate are measured with specially developed techniques, including a multidetector data acquisition system, a spectrum weighting function method, and a ramp-controlled high-voltage system. Measured parameters are compared among three different configurations of the experimental system and also with the results of a closed geometry with a point source. A calculation with the GMVP Monte Carlo code that uses the JENDL-3 nuclear data library is performed and shows agreement within 10%. The current experiment provides unique data for a higher step of benchmark to test the ability of neutronics design calculations for a realistic tokamak reactor.