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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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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. V. Subbaiah, A. Natarajan, D. V. Gopinath
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 352-370
Technical Paper | doi.org/10.13182/NSE89-A23624
Articles are hosted by Taylor and Francis Online.
Modifications to the computational scheme of the existing slab geometry gamma-ray transport code ASFIT are introduced to facilitate the inclusion of coherent scattering contributions. The revised code is tested with two model problems and subsequently is used to investigate quantitatively the transport effects of coherent scattering as a function of the incident photon energy and the atomic number Z of the medium. The shield materials studied in this respect are beryllium, aluminum, iron, molybdenum, tin, tungsten, lead, and uranium, and the incident photon energies range between 0.015 and 0.3 MeV. The system studied is a 48-mfp-thick slab, embedding a thin strip of isotropic source located 4 mfp from the left boundary. Plane parallel incident fluxes have also been studied in certain instances. The results of the computation are presented in the form of scattered flux spectra and dose rates, both at several depths inside the media. Tables of point isotropic source buildup factors including coherent scattering are also presented. It is observed that the addition of coherent scattering does not alter the shape of the flux spectrum significantly, but changes only the magnitude. Except for a small distance near the source, these changes in flux and hence dose are downward at all depths, becoming appreciable at large depths. Furthermore, the magnitude of the reduction varies essentially according to the ratio of the coherent scattering to the total cross section (ΣR/Σt)
