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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.
P. F. Windhofer, N. Pucker
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 223-233
Technical Note | doi.org/10.13182/NSE85-A27444
Articles are hosted by Taylor and Francis Online.
Multiple-collision solutions of the time-, space-, and angle-dependent neutron transport equation in slab geometry are given. Two different monodirectional sources have been used: (a) a δ(t)-shaped pulse of neutrons [δ(t): Dirac delta distribution] impinging on the slab at time t = 0, and (b) a “rectangular” source, emitting neutrons for a time interval Δt, describing a somewhat more realistic situation. Detailed results up to collision order three are discussed and exhibited in several figures. Interestingly, the “scalar” flux of one-time-scattered neutrons for the slab problem turns out to be independent of space in the region influenced by the slab boundaries.
