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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. 6LiF 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 10B disc. Both TLD and CR‐39 dosimeters were successful in detecting scattered neutrons in radiotherapy rooms.