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Updated: Jan 19, 2026

Neutron Crystallography Data Collection and Processing for Modelling Hydrogen Atoms in Protein Structures
Published on: December 1, 2020
Thermal Neutron Characterization and Dose Modeling of a 239PuBe Alpha-Neutron Source
Adam H Willey1,2, Timothy A DeVol1,2, Nicole E Martinez1,2
1Department of Environmental Engineering and Earth Sciences, Clemson University, Clemson, SC 29631.
Abstract:
Determination of neutron dose can be challenging and requires knowledge of neutron flux as a function of energy. The goal of this project was to characterize the thermal neutron flux of a 37 GBq PuBe alpha-neutron source and model the associated neutron dose using version MCNPX of the Monte-Carlo N-Particle transport codes. The PuBe source was placed in a neutron howitzer, and foil activation (dysprosium foils with and without cadmium covers) was used at various distances to determine thermal neutron flux, which was then used to verify the MCNPX model representing the system. The model was then adapted for dosimetric modeling to enable future neutron dose-response studies.
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