A study of accelerator driven sub critical system - material using the CASCADE code

摘要

In the existing situation of experimental data required for design and modeling of ADS andudsimilar other applications, development and benchmarking of the simulation codes for providingudreliable data has become essential. Amongst the intra nuclear cascade codes, CASCADE codeudwhich has been validated for the neutron production in proton collision with the high Z materialsudin the past, has been used to study nuclear behavior of some of the prominent ADS materialsudlike, Th, U, Pb, Bi, W, Fe, Cr and Al in respect of reaction and production cross sections ofudisotopes and neutrons in a wide range of energy, 11 MeV to several GeV. Emphasis has beenudlaid on the data of cross sections of (n, xn) reactions. It is found that their role is definite andudeffective in deciding fuel combinations. The code provides neutron cross section data whichudshows agreement with the existing experimental data and stresses need of further validationudusing precision data from the accelerators.