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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
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.
