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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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
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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.
G. Winkler, V. Spiegel, C. M. Eisenhauer, D. L. Smith
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 415-419
Technical Note | doi.org/10.13182/NSE81-A21377
Articles are hosted by Taylor and Francis Online.
The average cross section for the reaction 63Cu(n, α)60Co has been measured absolutely in the 252Cf spontaneous fission neutron field by activation in compensated flux geometry with an accuracy of ∼2.4% (1α). A near-point source of 252Cf and a light mass source-detector assembly in a low-scattering environment was used. The resulting cross-section value was compared with calculated values obtained by convoluting the spectral distribution of 252Cf neutrons with existing energy-differential data for the reaction 63Cu(n, α)60Co. There is very good agreement (within 5%) between the experimental and the calculated average cross section if the results from a recent measurement of the 63Cu(n, α)60Co excitation function are used. Thus the reaction 63Cu(n, α)60Co, which is an important threshold reaction in reactor dosimetry, fulfills the conditions for a Category I neutron-dosimetry reaction for fission reactor applications.
