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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.”
L. Garzotti, P. Innocente, S. Martini
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 505-509
Fueling and Tritium Handling Technology (Poster Session) | doi.org/10.13182/FST98-A11963662
Articles are hosted by Taylor and Francis Online.
In the RFX reversed field pinch (RFP) frozen H and D pellets with mass ≤5·1020 atoms and speed ≤1.5 km/s are used for plasma fuelling. If a high speed pellet is launched with no plasma or is not completely ablated, the graphite first wall may be damaged by its impact. The paper presents the design of a protection system, based on real-time measurements of plasma current and density, developed to prevent incomplete pellet ablation.