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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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.”
Paul W. Humrickhouse, Paul P. H. Wilson
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 166-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3754
Articles are hosted by Taylor and Francis Online.
A model of the University of Wisconsin Nuclear Reactor has been developed using MCNP5. Benchmarking of the model has centered on available reactor operations data from the original loading of the current TRIGA Fuel Life Improvement Program core, including control element differential worth curves and axial flux maps. By simulating the experimental measurement procedure for control element worth, integral worth values obtained for three control blades are within 6% of measured values. The comparison of simulated and measured axial thermal flux profiles suggests the need to improve the definition of the core temperatures and detailed isotopics. Future plans include modeling full-power (1 MW), high-temperature operation and burnup calculations to obtain current fuel definitions.