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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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 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. 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.”
Duck-Hoi Kim et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 118-122
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12337
Articles are hosted by Taylor and Francis Online.
Since the recommendation of blanket redesign by 2007 ITER design review, the blanket system has been developed in the framework of blanket integrated product team composed mainly of ITER organization and procuring parties. As a part of blanket conceptual design tasks, Korea domestic agency has supported the design analyses with respect to the hydraulic and thermal performance of the inboard blanket shield block.Three dimensional thermo-hydraulic and thermo-mechanical analyses of the inboard conceptual model with the poloidal cooling concept were performed. Two kinds of operation scenarios, inductive and non-inductive operations, were considered as representative loading conditions. The pressure drop, heat transfer and coolant uniformity in cooling passages were investigated in detail. The stress evaluation according to relevant code and standard was carried out and thermal bowing at flexible supports was also investigated. This paper presents the detailed analysis results, identifies issues on the conceptual configuration and makes suggestions on design improvements. In addition, this manuscript briefly describes about the complementary study such as the comparison of heat transfer coefficients calculated by empirical formula and CFD, and the effect of surface roughness inside the cooling channels.