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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
V. Marinelli, A. Pellei, P. Vallero, C. Vitanza
Nuclear Technology | Volume 27 | Number 2 | October 1975 | Pages 207-215
Technical Paper | Reactor | doi.org/10.13182/NT75-A24287
Articles are hosted by Taylor and Francis Online.
The (X, LB) correlation, which is currently used to predict the critical heat flux (CHF) onset in simple and complex geometries under a steady-state regime, is capable of a dynamic interpretation. The two-phase flow mean particles, climbing the channel at linear velocities corresponding to their mass velocity and local densities, reach the CHF conditions—i.e., zero thickness of the liquid film on the rod—when they have traveled a certain distance and have achieved a certain quality. According to this model, the CHF would be predicted in transient condition, when the boiling length and the mass velocities change with space and time, by applying the steady-state CHF (X, LB) correlation to the actual paths of the mean fluid particles. The calculations performed in comparison of the “Lagrangian point of view,” outlined above by means of the DOLCE computer code, with the local space-time approach of the “Eulerian point of view” indicate that the two methods give substantially equivalent results and predict satisfactorily the onset of the transient CHF for the Centro Informazioni Studi Esperienze annuli experimental data and General Electric Company 16-rod bundles data under typical boiling water reactor transients, including loss-of-coolant accident simulations.