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Radiation Protection & Shielding
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. M. Bansal, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 367-374
Technical Paper | doi.org/10.13182/NSE79-A19954
Articles are hosted by Taylor and Francis Online.
Some results of a detailed study of neutron diffusion in water containing 1/v and non-1/v absorbers are reported. We have solved the Boltzmann transport equation in the diffusion approximation using the multigroup method and the recent neutron scattering kernel proposed by the authors. The calculated values of diffusion length, L(T), in pure water in the temperature range from 0.5 to 60°C are found to be in good agreement with most of the experimental results. (Results based on the Nelkin kernel are consistently higher.) The variation of L(T) is nonlinear up to 10°C, but in the temperature range from it can be expressed as L(T) = L (10°C) + 0.00446 (T − 10). The computed values of the diffusion length in water poisoned with various concentrations of boron are consistent with the experimental results of Martinho and Costa Paiva. For non-1/v absorbers—cadmium and gadolinium solutions—calculations on space-dependent neutron spectra are reported. The calculated values of for various concentrations of cadmium and gadolinium are in good agreement with the experimental data of Goddard and Johnson. For high concentrations of cadmium, notable differences are observed between the present calculations and those based on the Nelkin kernel.