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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
R. L. Perel, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 124 | Number 1 | September 1996 | Pages 197-209
Technical Paper | doi.org/10.13182/NSE96-A24235
Articles are hosted by Taylor and Francis Online.
Hall’s differential operator method for the Monte Carlo calculation of sensitivities was extended so as to apply to point-detector-type problems. By this method, the evaluation of the sensitivities of the detector response (or, equivalently, those of the neutron flux at the detector) to material parameters of interest (cross sections, average number of fission neutrons, number densities) is concurrent with that of the very response. In such a Monte Carlo game, the neutron histories, or paths, are sampled, collision by collision, and the calculated contributions of each collision to the response and to its partial derivatives with respect to the parameters of interest are accumulated. For each path, these sums are the estimates for the response and its respective sensitivities. The Monte Carlo evaluations are then the respective averages of the individual path estimates. This procedure was applied to the analysis of the time-of-flight spectra of the leakage from several of the Livermore pulsed spheres. As an illustration, measured and calculated spectra and some calculated sensitivities are depicted and discussed.