Simulation of neutron transport in the reactor shielding material has been undertaken using ELSCAT code. ELSCAT utilizes Monte Carlo application which involve simulation techniques such as: the use of random number for a pdf (probability density function) sampling; tracking a particle life from its born to the end of its life; and statistical error calculation. In general, ELSCAT estimates the average number of elastic collisions needed to slow down the neutron from its source energy (Es) to its terminal energy (Emin) inside a moderator with mass number A. To determine the post collision energy, the appropriate pdf is sampled using random number generated by computer. This code also computes the average neutron scattering angle. In this simulation, have been obtained computational results of the average number of elastic collisions and average cosinus elastic neutron scattering angles for shielding materials with mass numbers: 238.0, 207.0, 56.0, 23.0,12.0, 9.0, and 1.0
Muhammad B. Setiawan
Muhammad B. Setiawan
