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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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 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. 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 E. Sawan
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 766-770
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9002
Articles are hosted by Taylor and Francis Online.
Data for 40 of the 71 isotopes/elements in FENDL-2.1 were taken from ENDF/B-VI.8. Following the release of ENDF/B-VII.0 we performed a preliminary assessment for changes made in data of these 40 isotopes/elements. We compared the relevant cross sections in the two libraries. In addition, we carried out MCNP calculations for a calculational benchmark representative of an early ITER design that was utilized during the FENDL development process. In addition, we performed 3-D calculations for an inertial fusion power plant conceptual design. It is concluded that modifying FENDL-2.1 to include the most recent ENDF/B-VII.0 is not urgently needed for ITER analysis. On the other hand, the larger changes in calculated ICF target neutronics parameters and tritium breeding ratio confirm the need for updating FENDL-2.1 for use in analysis of fusion systems beyond ITER. Additional calculations are in progress for integral experimental benchmarks to fully understand the impact of data changes introduced in ENDF/B-VII.0.