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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.
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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Latest News
Construction begins on Kairos’s fluoride salt–cooled test reactor
Earlier today, on a site in Oak Ridge, Tenn., that was formerly home to the K-33 Gaseous Diffusion Plant, Kairos Power marked the start of construction on its low-power demonstration reactor. Named Hermes, the 35-MWt test reactor claims status as the first Gen IV reactor to be approved for construction by the Nuclear Regulatory Commission and the first non–light water reactor to be permitted in the United States in more than 50 years.
Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 273-284
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3987
Articles are hosted by Taylor and Francis Online.
In this study, calculations were performed to simulate a postulated large-break loss-of-coolant accident for the High Flux Reactor (HFR) cooling system using the COBRA-TF computer code. COBRA-TF has been chosen for this analysis since it has suitable and validated two-phase flow models and critical heat flux (CHF) correlations for channels having small hydraulic diameters. Calculations have been performed to determine the CHF margins for the HFR. Six types of calculations were performed to provide a range of CHF margins. All COBRA-TF calculations indicate that margin does exist to the CHF limit for the small-hydraulic-diameter highest-power HFR channel. The range of margin is 2.1 to 1.3 times the nominal power of the highest power channel, depending on the boundary conditions and CHF correlation used. The range of margin identified in the HFR analysis is consistent with the margin values used in commercial nuclear power plants.