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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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.”
Jean-Claude Nimal
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 405-410
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9217
Articles are hosted by Taylor and Francis Online.
NAÏADE 1 shielding experiments were performed in the shielding laboratory at the Commissariat à l'Energie Atomique (French Atomic Energy Commission) in Fontenay aux Roses during the period 1965-1970. These experiments consisted of studying either the pure thermal neutron attenuation or the fission neutron attenuation in various materials such as water, iron, graphite, concrete, and multilayer shields. A reassessment of the experimental results was made between 2003 and 2005, and the results were evaluated again during the period 2007-2008. For each experimental configuration, the fission neutron source of a converter was calculated by using the TRIdimensionel POLYcinétique (TRIPOLI-4) Monte Carlo code. A part of the experimental results has been compared to the results of TRIPOLI-4. This work will be continued to analyze other benchmarks with integration into the Shielding INtegral Benchmark Archive Database (SINBAD).