Response of TLD‐600/TLD‐700 and CR‐39 to neutrons for medical dosimetry
Nabil El‐Faramawy, Vibha Chopra, Shrouk Rawash, Arafa Abd El‐Hafez, S.J. Dhoble
Abstract
Abstract In this study, thermoluminescence detectors (TLD)‐600 and TLD‐700 were used under different conditions to study neutron dosimetry for its application in medical dosimetry as albedo dosimeters. 6 LiF has a high cross‐section for neutrons and is more sensitive to neutrons than to gamma radiation. Conversely, TLD‐700 showed a better response to gamma radiation. Therefore, to obtain the response for neutrons, the responses for TLD‐600 and TLD‐700 were subtracted. A cadmium sheet was used to absorb incident thermal neutrons so that detector measured only backscattered neutrons from the albedo dosimeter. A Perspex sheet was used as a moderator to thermalize the fast neutron source Am‐Be used in the experiment. CR‐39 was used to detect fast neutrons and act as an albedo dosimeter when covered with a 10 B disc. Both TLD and CR‐39 dosimeters were successful in detecting scattered neutrons in radiotherapy rooms.