Monte Carlo simulation of biological shielding parameters in PGNAA

Abstract

A prompt γ neutron activation analysis (PGNAA) facility based on a 252 Cf spontaneous fission neutron was performed with the final goal of obtaining various optimised radiation protection design parameters. MCNP Monte Carlo code was used to simulate the lead (Pb) shield thickness on two sides of the sample chamber, and B 4 C, B 2 O 3 , LiOH, LiF, and borax were selected as neutron-absorbing materials that were simulated to determine optimal parameters for the optimal design of a biological multilayer composite shield. A series of calculations performed with the MCNP code indicated that the 5 cm thick Pb innermost layer of a biological shield rapidly reduced fast neutrons, and a moderation layer of 25 cm thick paraffin, 20 mm thick borax, and 2 mm thick B 4 C were selected as neutron-absorbing materials. The calculated biological shield protection parameters satisfied the requirements of the PGNAA facility used in the experiment.

Overview of Industrial Materials Detection Based on Prompt Gamma Neutron Activation Analysis Technology

“…Since the first use of PGNAA technology to detect elements in 1936, the application research of PGNAA technology has started abroad [10] [11] [12]. In recent years, with the development of nuclear electronics instruments, the detector's ability to detect γ rays has been continuously improved [13], and the rapid development of technologies such as neutron beam devices [14] [26]. At this time, with the development of radioisotope neutron sources [27] and portable neutron generators [28], the technology has been able to conduct in-situ and rapid online analysis of large samples such as mining [29] [30], biological [31], manufacturing and construction quality control tasks [32] [33] [34], as well as homeland security contraband detection [35].…”