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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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May 2025
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.
Yu. S. Lyutostansky, V. I. Lyashuk
Nuclear Science and Engineering | Volume 117 | Number 2 | June 1994 | Pages 77-87
Technical Paper | doi.org/10.13182/NSE94-A20074
Articles are hosted by Taylor and Francis Online.
The possibility of constructing an intense hard-spectrum neutrino source based on the β‾ decay of 8Li (T1/2 = 0.8 s) is studied. Applications of such a source are considered in neutrino investigations. The source can be developed on the basis of a neutron-to-antineutrino lithium converter through (n, γ) activation of 7Li isotopes irradiated by neutrons from the active zone of a reactor. The physical parameters of the lithium converter are compared with those of other neutrino sources. Different geometries for a converter using heavy water are considered. The converter efficiency is calculated as a function of the purity of the 7Li isotope and the expected tritium activity values. The cross section of the neutrino-deuteron reaction increases rapidly in both the neutral ( + d → n + p + ) and the charged ( + d→ n + n + e+) channels as the converter efficiency is improved. The real efficiency is 9%, and the cross sections are enhanced by factors of 2.5 and 5 in the respective channels.