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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Michael F. Roche, Leonard Leibowitz, Jack L. Settle, Carl E. Johnson, Richard C. Vogel, Robert L. Ritzman
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 96-116
Technical Paper | Material | doi.org/10.13182/NT91-A35536
Articles are hosted by Taylor and Francis Online.
The vaporization of strontium, barium, and lanthanum from mixtures of their oxides with urania, zir-conia, and concrete is determined with the objective of understanding the release of these refractory fission products during the core/concrete interaction phase of a degraded core accident. The vaporization of uranium and the total mass vaporized are also determined. Three different concretes having silica contents ranging from 7 to 69 wt% are used to reflect the known range of reactor basemat compositions. In the experiments, the mixtures are vaporized at 2150 or 2400 K into flowing H2 or He-6 H2 gas. The total mass of material that was vaporized is determined by weighing the condensates; the masses of individual elements are determined by chemical analyses of the condensates. The phases present in the heated mixtures are inferred from electron probe microanalyses and X-ray diffraction analyses. Equilibrium calculations are performed using SOLGASMIX and a thermodynamic data base containing 112 gaseous and 108 condensed species. The partial molar free energy of oxygen is calculated from the equilibrium oxygen pressure established in the high-temperature reaction zone between the gas and the sample. Using this experimental data, the release to be expected in the molten core/concrete interaction phase of a severe nuclear reactor accident is estimated. The estimated release of strontium, barium, lanthanum, and uranium is <1% with a basemat concrete of low silica content (7 wt%) and decreases to <0.01% with a basemat concrete of high silica content (69 wt%). The estimated total mass release is ∼0.5% with all three concrete types.