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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.
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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.
David A. Rehbein, Roger W. Carlson
Nuclear Technology | Volume 31 | Number 3 | December 1976 | Pages 348-356
Technical Paper | Fuel | doi.org/10.13182/NT76-A31671
Articles are hosted by Taylor and Francis Online.
Many thermal-hydraulic computer codes employ a fuel rod heat transfer model to couple the fuel rod temperatures with the hydraulic driving forces. Frequently, these models utilize uniform thermal conductivity for the fuel to reduce computer usage and storage. To evaluate the effect of this modeling, the uniform thermal conductivity model in COBRA III was modified to incorporate temperature-dependent thermal conductivity utilizing the complete expansion of the gradient of the heat flux, including the term that represents the gradient of the thermal conductivity. Demonstrative calculations for two transients showed that the peak fuel temperatures are very dependent upon the nonuniformity of the thermal conductivity. However, the peak cladding temperatures are almost independent of modeling of the thermal conductivity of the fuel because the clad temperatures are determined by the clad properties and the total amount of heat being transferred from the fuel to the coolant. The heat transferred is proportional to the integral of the thermal conductivity, which is virtually independent of the specific dependence of the temperature dependence of the thermal conductivity. The intermediate approach that employs the correct thermal conductivity at each point in the calculation but ignores the term in the heat conduction equation that accounts for the variation in the thermal conductivity was shown to yield results that are very similar to the uniform thermal conductivity cases. It is concluded that a uniform thermal conductivity model is adequate for models that are intended for the analysis of transients where the limiting constraint is the peak cladding temperature, such as the loss-of-coolant accident. However, models that are intended for the analysis of transients where the peak fuel temperature is limiting should employ the temperature dependence of the thermal conductivity.