Monte Carlo Study of an Electron-Based Neutron Source for Bragg Edge Imaging

Abstract

Neutron imaging is a powerful and nondestructive tool for testing materials in industrial and research applications. Compact accelerator neutron sources are gaining interest in neutron application techniques, such as Bragg edge transmission imaging. Delivering a high neutron flux with a narrow pulse width and suppressed photons at the sample position are fundamental factors for designing a neutron source for Bragg edge imaging. In this study, Monte Carlo calculations were performed to simulate a 40-MeV electron beam impinging on a cylindrical tungsten target. Different target moderator and reflector (TMR) geometries were investigated to produce cold neutrons, and their results were compared. Polyethylene (PE) and graphite were used as the moderator and the reflector, respectively. The structures and dimensions of the moderator and reflector were optimized using a Monte Carlo simulation with the PHITS-3.28 code. The effect of the PE moderator temperature on the cold neutron flux was investigated. The results showed that the optimum size of the PE at 77 K inside the reflector was 3 $\times$ 15 $\times$ 15 cm³ to achieve the wavelength resolution of 1.05% and the neutron flux of 1.16 $\times$ 10⁴ n/cm²/s at 1000 cm from the target station by assuming the electron beam current of 275 µA. In addition, the FLUKA 4-2.1 code was used to calculate the neutron spectrum from the designed neutron production target at room temperature, and the results were consistent with the PHITS calculations. The neutron spectrum together with its pulse width from the designed TMR were used to simulate the Bragg edges of an $\alpha$-Fe sample, and it was concluded that the TMR is suitable for performing Bragg edge imaging.

Keywords:

• Bragg edge imaging
• CANS
• photonuclear reaction
• PHITS
• FLUKA

Acknowledgments

The authors would like to thank Prof. Hirotaka Sato from the Graduate School of Engineering, Hokkaido University, Japan, for his valuable discussions and also for providing the experimental data. This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commission (NSSC) of Republic of Korea (Grant No. 2204018).

Disclosure Statement

No potential conflict of interest was reported by the authors.

Correction Statement

This article has been corrected with minor changes. These changes do not impact the academic content of the article.