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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Latest News
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.
K. D. Lathrop
Nuclear Science and Engineering | Volume 21 | Number 4 | April 1965 | Pages 498-508
Technical Paper | doi.org/10.13182/NSE65-A18794
Articles are hosted by Taylor and Francis Online.
The effects of anisotropic scattering approximations in the monoenergetic transport equation are evaluated by calculating discrete eigenvalues, fluxes due to a plane source, and slab critical half-thicknesses, all for homogeneous media. Relative to P2 scattering approximation results, which are deemed accurate because of their agreement with P4 solutions, the simple transport approximation overestimates eigenvalues and underestimates half-thicknesses in multiplying media while a P1 scattering approximation underestimates eigenvalues and overestimates thicknesses, but with smaller error. In the plane source problem, where the detailed flux behavior is observed, the transport approximation is even less accurate; but an extended transport approximation is found to be much more adequate. In overall effectiveness, in order of increasing accuracy, the approximations considered are ranked as follows: 1) transport, 2) forward-backward, 3) first-order Legendre, 4) extended transport, and 5) higher order Legendre. Some evidence is given to indicate that, even for severely anisotropic scattering, relatively low-order Legendre approximations are sufficient to include anisotropic scattering effects.