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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.
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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.
R. Gwin, R. R. Spencer, R. W. Ingle
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 365-379
Technical Paper | doi.org/10.13182/NSE86-A18347
Articles are hosted by Taylor and Francis Online.
A series of experiments was performed to measure the dependence on the incident neutron energy of the average number of prompt neutrons emitted per fission from 233U, 235U, and 239Pu relative to the average number of prompt neutrons emitted in spontaneous fission of 252Cf. The incident neutron energy range was 0.0005 to 10 MeV. A white neutron source was generated by the Oak Ridge Electron Linear Accelerator, and the energies of the neutrons incident on the fissile samples were determined by time-of-flight techniques. In each experiment the samples, including the 252Cf standard, were contained in a fission chamber surrounded by a large volume (0.91 m3) of liquid scintillator loaded with gadolinium. The fission chamber detected the fission events, and the scintillator detected the accompanying prompt neutrons. The resulting data were analyzed to yield: p(E) = p(E) (fissile)/p(252Cf). For 235U and 239Pu our results overlap, within the experimental uncertainty, the results of the evaluation of Manero and Konshin (1972), and in the case of 235U our data show the same general structure apparent in the evaluation up to 0.5 MeV. Our p(E) for 233U does not show the structure near 0.2 MeV obtained by Manero and Konshin.