Abstract
This work gives the total dose and the spectral distribution at any specific point inside a tissue equivalent cylindrical phantom due to Pu–Be neutron source. The absorbed dose through the material are coming from 17 reactions between the neutrons and the phantom constituents: H 2,0 2,N 2. and C. The changes in the neutron spectra are due to energy loss as a result of neutron slowing down. A computer program is used to carry out these calculations using the Monte-Carlo technique.
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