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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
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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.”
Fabrice Bentivoglio, Nicolas Tauveron
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 55-75
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4008
Articles are hosted by Taylor and Francis Online.
In the framework of Generation IV, the Commissariat à l'Energie Atomique studies different concepts of gas-cooled reactors (GCRs). The estimation of thermal-hydraulic performances in steady-state and in transient operations is of high importance for the designer of such systems. These evaluations require efficient and reliable simulation tools capable of modeling the whole reactor, including the core, the core vessel, the piping, the heat exchangers, and the turbomachinery. CATHARE2 is a thermal-hydraulic one-dimensional reference safety code developed and assessed for pressurized water reactors. It has been adapted to deal also with GCR applications. The assessment for these new applications requires cross comparisons with experimental representative data. Thus, CATHARE2 is validated against existing experimental data, in particular, the German power plant Oberhausen II data. Oberhausen II was a 50-MW(electric) direct-cycle helium turbine plant, operated by the German utility Energie Versorgung Oberhausen. This paper presents the plant, with a large emphasis on the helium power conversion unit, the modeling, and the comparison between experimental data and simulation results for both steady-state and transient cases. The agreement between the experimental data and the CATHARE results is quite satisfactory for the analyzed cases.