عنوان مقاله [English]
نویسندگان [English]چکیده [English]
Time-dependent behavior of fission reactors is simulated using Monte Carlo method and a code named TDMC is developed for neutron parameters calculations. Parameters such as reactivity, neutron life time, space distribution of flux, and power with several groups of delayed neutrons are calculable by the code. Material composition and system boundaries may be changed as time-dependent in the code. The results which have obtained with the code are in good agreement with the benchmark problems results.
10. Z.A. Akcasu, G.S. Lellouche, S. Gerald, L.M. Shotkin, “Mathematical methods in nuclear reactor dynamics,” ACADEMIC Press, INC, U.S. (1971).