ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
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 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.”
Taisuke Yonomoto, Masaya Kondo, Yutaka Kukita, L. Scott Ghan,, Richard R. Schultz
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 112-122
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35380
Articles are hosted by Taylor and Francis Online.
Integral experiments simulating small-break loss-of-coolant accidents in the Westinghouse AP600 reactor are conducted using the ROSA-V large-scale test facility. These experiments show that the core makeup tank (CMT) behavior can be divided into two phases: the natural-circulation and the drain phases. The natural-circulation phase between the CMT and the rest of the primary is established immediately after the opening of the valve in the discharge line. The hot water from the primary, through the pressure balance line (PBL), accumulates in the top of the CMT, forming a clear thermal stratification above the cold initial inventory of the CMT. The drain phase is initiated by flashing in the CMT for break diameters ≤1 in. and by a gaseous flow from the primary for break diameters ≥2 in. Interactions between the CMT and the other safety components are observed: The CMT discharge rate is decreased by accumulator injection and is increased by actuation of the automatic depressurization system. When the PBL is empty of liquid, the CMT drain rate is approximately given by the free gravitational drain rate, irrespective of the flow direction in the PBL.