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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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.”
Seok-Hee Ryu, Kil-Sup Um, Jae-Il Lee
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 163-172
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-28
Articles are hosted by Taylor and Francis Online.
To evaluate the effect of thermal conductivity degradation for high-burnup fuel, a postulated control element assembly (CEA) ejection accident is assessed with the SPACE (Safety and Performance Analysis CodE) code. The SPACE code, which is currently under development as a safety analysis code for nuclear power plants, can predict thermal-hydraulic responses of the nuclear fuel and nuclear steam supply system during design basis accidents with two-fluid, three-field governing equations. Fuel performance behaviors during the CEA ejection accident using six fuel conductivity models including the burnup-independent reference conductivity model, the Lyons model, are investigated and compared with results of the reference model within the range from 0 to 30 GWd/tonne U. The Oak Ridge National Laboratory model predicts the highest peak fuel centerline temperature of 4531°F at 0 GWd/tonne U, and the modified Nuclear Fuels Institute model shows the uppermost value of 4796°F, which is 364°F higher than the reference model at 30 GWd/tonne U. It is also observed that the peak fuel centerline temperature increases linearly with fuel burnup and that the maximum increase rate of the peak centerline temperature per fuel burnup is ∼11.6°F per GWd/tonne U. For all thermal conductivity models, the maximum radial average fuel enthalpies are <230 cal/g, and the rise in radial average fuel enthalpy during the CEA ejection accident still remains within the pellet-cladding-mechanical-interaction failure criterion.