The paper describes the production of the custom-made source and its characterization by means of , dose rate and neutron source strength measurements. From measurements it was deduced that activity transfer from the initial solution to the final source was (at 68%C.L.) and the final activity was (5.41卤0.30) MBq. The dose rate was measured with two dosimeters yielding 12.1 mSv/h and 14.3 mSv/h in 1 cm distance. The neutron source strength of the 5.41 MBq 228Th source was determined to be (6.59卤0.85) s鈭?.