Author(s)

Rasha Ali El-Tayebany, Hekmat Elbegawy

Nuclear and Radiological Safety Research Center, Egyptian Atomic Energy Authority, Cairo, Egypt.

Many scientific domains use gamma-ray spectrometry, but non-destructive gamma scanning and gamma emission tomography of radioactive fuel in particular. In the experimental setting, a collimator is frequently employed to focus on a particular location of interest in the fuel. Predictive models for the transmitted gamma-ray intensity through the collimator are required for both the optimization of instrument design and the planning of measurement campaigns. Gamma-ray transport accuracy is frequently predicted using Monte Carlo radiation transport methods, but using these tools in low-efficiency experimental setups is challenging due to the lengthy computation times needed. This study focused on the full-energy peak intensity that was transmitted through several collimator designs, including rectangle and cylinder. The rate of photons arriving at a detector on the other side of the collimator was calculated for anisotropic source of SNM (U₃O₈). Some geometrical assumptions that depended on the source-to-collimator distance and collimator dimensions (length, radius or length, height, and width) were applied to achieve precise findings.

Monte Carlo, High Purity Germanium (HPGe), Collimator, Uranium

El-Tayebany, R. and Elbegawy, H. (2023) Assessment of Modeling Collimator Designs for Gamma-Ray Transmission of Uranium Oxide Spectrometry Using HPGe Detectors. World Journal of Engineering and Technology, 11, 663-671. doi: 10.4236/wjet.2023.114044.