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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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.”
Takaaki Mochida, Katsumasa Haikawa, Jun-Ichi Yamashita, Akira Nishimura, Yutaka Iwata, Shiroh Arai
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 91-107
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35314
Articles are hosted by Taylor and Francis Online.
A boiling water reactor (BWR) core design for better uranium utilization is presented, and its validity is demonstrated through simulation and operation data. Together with the axial power flattening obtained by an axially zoned enrichment core, uranium utilization improvement techniques such as an axial blanket for neutron leakage reduction, a low leakage loading pattern, an improved local enrichment distribution in the fuel bundle, and spectral shift operation method are promising design features to be applied to the BWR core. Quantitative studies for the amount of burnup increase and power peaking rise are made to estimate a level of effective uranium utilization. The improvements in uranium utilization are confirmed not only in the computational core design study, but also in empirical data from a commercial BWR. Operating experience proves the adequacy of the core design. A uranium utilization improvement of >10% is obtained without a loss of load factor.