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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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.”
S. Chatzidakis, A. Ikonomopoulos, M. Alamaniotis
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 392-406
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14171
Articles are hosted by Taylor and Francis Online.
A systematic approach for performing a holistic reactivity insertion analysis in research reactors using the RELAP5/MOD3 code is proposed. The intention is to demonstrate, in an orderly manner, a method for determining the limiting reactivity insertion in a research reactor facility. Indispensable constituents of the algorithmic approach are the introduction of the "time-to-failure" parameter, the selection of the reactivity insertion duration, the evaluation of the control rod drop time, and the computation of engineering factors. The methodology is demonstrated through a RELAP5/MOD3 parametric study performed to determine the limiting reactivity insertion values for the Greek Research Reactor-1 (GRR-1). In the framework of this study, the core nodalization effect on reactivity limits and the degree of conservatism introduced by the engineering factors are discussed. The results obtained confirm the applicability of the approach and reveal the effect of the parameters mentioned above on the performance of reactivity insertion analysis.