Abstract

In this article, a computer model for a thermal-neutron dosimeter, using an electrochemically etched CR-39 detector with a LiF converter screen, is presented. Our calculations indicate that a ∼ 0.13 μm thick LiF converter screen used in conjunction with the CR-39 detector would provide a dose-equivalent response to thermal neutrons which is of the same order as that for fast neutrons under similar processing conditions. The article then outlines our theoretical and experimental work concerning the influence of a water- as well as a tissue phantom on the response of a CR-39-based thermal-neutron dosimeter. Here, we have used the above phantoms in different thicknesses and have studied the albedo as a function of the phantom's thickness. Our results indicate that the contribution of the albedo neutrons to the response of the dosimeter, exposed to thermal neutrons on the human body, would be around 72%.

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