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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.”
R. Antidormi, E. Proust, N. Roux (2)
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 519-524
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30455
Articles are hosted by Taylor and Francis Online.
Since lithium-containing ceramics (e.g. Li2O, LiAlO2, Li4SiO4, Li2ZrO3, Li2TiO3) are considered as breeding materials in the blanket of the next generation fusion reactors, several studies are in progress to evaluate their behaviour under irradiation in both operating and accidental conditions. Based on safety and economic considerations tritium inventory and release are the most critical issues for blanket concept. Investigation of tritium transport processes by using comprehensive physical-mathematical models is one of the current activities in this area. Although some analytical models and numerical methods dealing with tritium transport and release in fine-grained ceramic were already developed and applied to interpret results from in-situ and/or post-irradiation annealing experiments, it is necessary that presently available computer codes enlarge their range of applicability to be able to predict, with increased accuracy, the tritium release response for a wider range of experimental conditions and material characteristics. This paper reviews the tritium modelling activity and summarizes the existing transport models and computer codes highlighting models development and focusing on major changes and evolutionary improvements.1 Validation of models by comparison of calculated results with experimental ones is also reported and discussed. Areas of future applications are identified and emphasis is placed upon the growing need of developing more accurate computer codes with the aim to improve the accuracy of blanket tritium inventory estimations.