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Generation of Radiation Transport Geometry from Computer-Generated Design Data

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2 Author(s)
Jones, L.Carol ; Sandia National Laboratories P. O. Box 5800 Albuquerque, NM 87185 ; McKeon, Donald C.

Monte Carlo simulation is a valuable tool for analyzing radiation effects in three-dimensional objects. Generating the geometry data necessary for describing solids to the simulation programs can be tedious and time consuming, and it is extremely error-prone. A faster, more accurate method of defining geometry data would speed up the radiation transport analysis process sufficiently for the analysis results to influence design. For computer-generated design data, manually defining the geometry data for radiation transport programs is an unnecessary step if software to translate the data into an appropriate format for the radiation transport calculations is available. This paper will present work on the translation of a particular type of computer-generated design data to a format suitable for the MORSE radiation transport code and will discuss applications for its use in radiation transport calculations.

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Nuclear Science, IEEE Transactions on  (Volume:31 ,  Issue: 6 )