Monte Carlo Simulation of Neutron and Photon Transport with Direct Utilization of Information from Evaluated Nuclear Data Files

The most advanced constant information related to the accuracy of calculations is available in files of nuclear data libraries. It is common practice in Monte Carlo to use routines of Constant Unit to simulate the process of particles interaction with substances and to solve neutrons and photons transport problem. It is a characteristic of Constant Unit to derive parameters directly from data files without any simplification. The main idea of the method proposed by us is to directly extract the values required from data files. The usual practice so far applied is that data processing is followed by the Monte Carlo method application in calculational efforts. The method being developed allows to directly utilize the data obtained from libraries and seems to be the most accurate technique. Moreover, the method proposed doesn’t introduce additional inaccuracy into the final results.