Monte Carlo simulation study on the 241Am-Be radionuclide source reference neutron radiation

Abstract

In order to study the feasibility of using lightweight 241Am-Be radionuclide reference neutron radiation field for the calibration of neutron measurement instruments, this paper reported the Monte Carlo simulation work on free field reference neutron radiation, standard reference neutron radiation regulated by ISO-8529 series standards and minitype reference neutron radiation we designed. The distributions of dose equivalent rates and neutron energy spectrum in different conditions, such as different room types, different room sizes and different shield materials were the main simulation contents for analyzing the characteristics of the three types of reference neutron radiation. According to the simulation results, theoretical supports were provided for the discussion on the minitype reference neutron radiation for calibration purpose.

Shielding design in neutron activation experiment system based on D-T neutron tube

“…There fore, it is nec es sary to study the en tire shield ing de vice. Bo ron-con tain ing poly eth ylene (BPE) is a new type of neu tron shield ing ma te rial, which is not only sig nif i cantly better than poly eth ylene in shield ing ther mal neu trons, fast neu trons and, gamma ra di a tion but also has good sta bil ity, cor ro sion re sis tance, elec tri cal in su la tion, wear re sis tance, and other ad van tages [14][15][16]. Be cause lead metal has a high den sity, lead is of ten used as a gamma shield [17].…”