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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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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. E. Titarenko, O. V. Shvedov, M. M. Igumnov, E. I. Karpikhin, V. F. Batyaev, V. I. Volk, A. Yu. Vakhrushin, S. V. Shepelkov, A. V. Lopatkin, S. G. Mashnik, T. A. Gabriel
Nuclear Science and Engineering | Volume 131 | Number 1 | January 1999 | Pages 96-106
Technical Paper | doi.org/10.13182/NSE99-A2020
Articles are hosted by Taylor and Francis Online.
Experimental determination of the resonance neutron absorption in a heavy water solution of 2.57 g/litre 237Np is presented. Experimental samples were irradiated in the MAKET critical plant. Prior to irradiation, 237Np was radiochemically purified to remove 233Pa. The experimental samples were prepared by evaporating two aliquot samples taken from the irradiated solution. The nuclide composition of the samples was analyzed using a GC-2518 Ge detector, a 1510 module, and an S-100 plate to emulate a multichannel analyzer in an IBM personal computer. The spectrometric resolution was 1.8 keV at the 1332-keV line. The gamma spectra were processed by the ASPRO code. The neutron flux was measured by two methods using Al + 55Mn + natCu + 197Au + natLu alloy foils.