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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 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.”
Koichi Maki
Fusion Science and Technology | Volume 12 | Number 2 | September 1987 | Pages 310-319
Blanket Engineering | doi.org/10.13182/FST87-A11963788
Articles are hosted by Taylor and Francis Online.
When a blanket concept is applied to the actual reactor design, various structural changes such as material thickness, material volume fractions, etc., are made to adjust the overall design to meet lifetime and material stress requirements. After these changes, the new tritium breeding ratio (TBR) is required to be easily and quickly estimated. Hence, an analytical TBR formula was derived by separating absorption, scattering, neutron multiplication, and tritium production cross sections at high energies above the multiplication reaction threshold from those at low energies near the thermal energy. The formula was applied to three blanket types. The TBR values calculated by this formula agreed with those of an ANISN transport code within 5%.