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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.”
K. R. Schultz, A. R. Veca, G. A. Deis, P. Y. S. Hsu, R. E. Nygren, H. Herman
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 763-768
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22952
Articles are hosted by Taylor and Francis Online.
The First Wall/Blanket/Shield (FWBS) Program has the goal to provide the development and testing of FWBS systems for magnetic fusion reactors. Program Element II of this program is to develop the thermal-hydraulic and thermomechanical data base for blanket and shield components. The critical blanket/shield data needs were identified, alternate techniques to simulate fusion neutron bulk heating were evaluated, and a detailed technical plan was developed. The initial focus is on the critical issues of solid breeder blankets. Two single effect scoping tests are currently in progress to determine the heat transfer characteristics and thermomechanical stability of the solid breeder bed. The design of an integral test to simulate all the non-nuclear aspects of the blanket has been completed. Preliminary planning for a fission reactor-based nuclear test has also been done. Future testing will investigate alternate solid breeder blanket materials and configurations and will begin the investigation of the critical MHD effects of liquid metal blanket concepts.