engleski

TOTAL AMBIENT DOSE EQUIVALENT BUILDUP FACTORS FOR PORTLAND CONCRETE

In this work, total ambient dose equivalent buildup factors for Portland concrete are calculated using MCNP6TM. Buildup factor calculations could approach intractable solutions in general as they depend on a large number of variables. These include geometry, source strength, and the composition of the shield (which itself can be heterogeneous). In this work, we considered 252 Cf and AmBe sources, as well as monoenergetic incident neutrons in the energy range from 0.025 eV to 14 MeV. The shielding material of interest was first taken to be standard Portland cement and then U.S. average earth was added to the Portland concrete as an aggregate. The transmitted neutron and gamma ray ambient dose rate was calculated first and then used for total buildup factor calculation. Perhaps more telling than the calculated theoretical buildup factor, the credible dispersion in expected resultant buildup factors was also calculated by conducting a very rudimentary sensitivity analysis. An additional aim of this work is to provide a model based on the machine learning technique called the Support Vector Regression (SVR) method in the calculation of concrete buildup factors.

buildup factor, radiation shielding, point kernel, monte carlo

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