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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
G. Breitbach, H. Barthels
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 392-399
Technical Paper | Reactor | doi.org/10.13182/NT80-A17687
Articles are hosted by Taylor and Francis Online.
In the case of hypothetical accidents, temperatures of ∼2000 to 3000°C are expected in the core of a pebble-bed high temperature reactor (HTR). At such high temperatures the transport of heat by radiation is the most important mechanism. For the calculations of temperature pattern in the reactor core, the effective thermal conductivity λeff of the pebble bed must be known. Two models predicting λeff are represented. They are the cell model of Zehner and Schluender and the modified radiation model of Vortmeyer, which has been extended to high temperatures. A transient measurement method was used to determine the effective thermal conductivity of pebble beds of graphite and of zirconium oxide at temperatures up to 1000 and 1500°C, respectively. The theoretical λeff values are compared with experimental results. The theoretical values of λeff predicted by the Zehner-Schluender formula are too low, while the λeff values of the modified radiation model are somewhat too high. Corrections to both formulas were made. Finally, it is demonstrated which values of λeff are predicted by high temperatures in the pebble bed of the HTR.