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
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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.”
Mohamed Tahar Sissaoui, Guy Marleau, Daniel Rozon
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 197-212
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2942
Articles are hosted by Taylor and Francis Online.
A new model has been developed to evaluate the variation of few-group cross sections with local parameters and the history of the reactor. This model allows us to generate a coherent set of nuclear cross sections for a CANDU cell. The history dependence of the nuclide concentrations is taken into account by creating a pseudo-isotope, which includes actinides whose concentrations are strongly affected by local parameter history. Simple physical considerations lead us to determine the law of variation of the cross sections as a function of these parameters. They permit the computation of the cross sections for each state of the reactor core, using a unique library for each type of cell, which contains the nuclear cross sections computed at nominal conditions and feedback coefficients. To validate the feedback model, several operational situations were tested, and the results are compared to those given by a transport calculation using the DRAGON cell code.