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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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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.”
H. Maekawa, S. Yamaguchia, C. Konno, Y. Oyama, Y. Ikeda, K. Sekiyamab, K. Kosako
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1949-1954
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29627
Articles are hosted by Taylor and Francis Online.
An integral experiment was performed on a Be cylindrical assembly of 630mm in diameter and 456mm in thick. Measured items were reaction rates, in-system neutron spectra and gamma-ray heating rates. The experimental analysis was performed by the MCNP and DOT3.5 codes using the nuclear data of JENDL-3, JENDL-3PR1, ENDF/B-IV and LANL. For high threshold reactions and integral flux above 10MeV, the calculation based on JENDL-3 agrees well with the experiment, while the calculations of ENDF/B-IV and LANL underestimetes those compared to the experiment. For integral neutron flux of 0.16∼0.5 MeV, the calculation of JENDL-3 agrees well with the experiment. But in the case of ENDF/B-IV the underestimation is 20%. It can be concluded that the nuclear data of Be in JENDL-3 improves very much in accuracy from the temporary version JENDL-3PR1.