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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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Nuclear Technology
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.”
J. W. Davidson, M. E. Battat
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 2007-2015
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29636
Articles are hosted by Taylor and Francis Online.
A precise calculational analysis of the INEL manganese bath experiment to measure beryllium neutron multiplication has been performed. The goal throughout the analysis was the minimization of all sources of error due to the calculational model and method. An extremely detailed three-dimensional Monte Carlo geometry model was developed for use with the code MCNP. Calculations were performed for a bare-source and four beryllium sample configurations for both DT and 252Cf neutron sources. The primary objective of the analysis was the calculation of various neutron-economy parameters applied as experimental corrections, either directly or as verification of measured values. The most significant of these were the tank leakage, duct streaming, structural absorption, fractional bath capture in manganese, high-energy parasitic bath absorption, neutron multiplication in other materials, and indirect absorption and multiplication in beryllium.