Overview of Monte Carlo radiation transport codes |
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Authors: | BL Kirk |
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Institution: | Radiation Safety Information Computational Center (RSICC), Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831-6171, USA |
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Abstract: | The Radiation Safety Information Computational Center (RSICC) is the designated central repository of the United States Department of Energy (DOE) for nuclear software in radiation transport, safety, and shielding. Since the center was established in the early 60’s, there have been several Monte Carlo (MC) particle transport computer codes contributed by scientists from various countries. An overview of the neutron transport computer codes in the RSICC collection is presented. |
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