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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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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
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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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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.
F. W. Staub, N. Zuber, G. Bijwaard
Nuclear Science and Engineering | Volume 30 | Number 2 | November 1967 | Pages 279-295
Technical Paper | doi.org/10.13182/NSE67-A17338
Articles are hosted by Taylor and Francis Online.
Experimental data are presented on the transient response of the vapor volumetric concentration in a boiling liquid. The experiments were conducted with Refrigerant-22 in forced upward flow through an electrically heated circular tube. The experiments were performed by oscillating the power input to the metal test section while maintaining a constant discharge pressure and a constant inlet liquid velocity. The amplitude of the power oscillations was varied between 5 and 40% of the average power at frequencies between 0.01 and 10 cps. Steady-state and transient void fractions were measured at six axial locations using a two-beam x-ray attenuation traverse method. Satisfactory agreement is shown between the results predicted by the void propagation equation and the experimental data. It is shown in particular that: 1) The rate of propagation of the voids as well as the wave form of the void disturbance as it propagates along the cluct can be predicted by means of kinematic waves 2) The void response depends upon the flow regime 3) Both the propagation velocity and the wave form can be predicted rather accurately if the effects of flow regime are taken into account. The loss of accuracy, introduced by not considering the effect of flow regime, is also demonstrated.