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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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June 2025
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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.
T. O. Passell, R. L. Heath
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 308-315
doi.org/10.13182/NSE61-A15372
Articles are hosted by Taylor and Francis Online.
Measured values of effective cross sections for fission neutrons obtained for n,p reactions on Ni58, Fe54, Zn64, Mg24, Fe56, Zn67, and Cu65 are 92, 54, 28, 1.2, 0.82, 0.57, and 0.36 mb, respectively. All cross sections are based upon the value 0.60 mb for the n,α reaction on Al27. Measurements were made at the exact center of the EBR-I core. This position has been shown by other investigators to have a neutron energy spectrum similar to that of virgin fission neutrons in the region above 2 Mev. The n,p reaction on Ni58 is shown to have unusual practical advantages as a fast flux monitor. The chemical and physical stability of nickel metal in most reactor coolants, the absence of radioactivities obscuring the Co58, the long half-life of Co58 (72 days), and the ease with which its 0.800 Mev gamma can be measured, are some of these advantages. A major but avoidable drawback is the 1650 barn thermal neutron capture cross section of Co58. A comparison of nickel and sulfur in measuring the fast neutron flux spectrum in beam hole HB-3 of the MTR is included. Evidence is presented which indicates that the correct value for the fission neutron cross section of S32 is 65 mb.