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Irradiator Commissioning and Dosimetry for Assessment of LQ α and β Parameters, Radiation Dosing Schema, and in vivo Dose Deposition
Published on: March 11, 2021
Radiation Dosimetry of a Graphite Moderated Radium-Beryllium Source
Norman E Holden1, Richard N Reciniello, Jih-Perng Hu
1*Brookhaven National Laboratory. Upton, NY 11973-5000.
Abstract:
The Brookhaven National Laboratory Sigma Pile is a radium-beryllium neutron source imbedded in a cube of graphite blocks. The pile is approximately 2.13 m on four sides and is 3.07 m high. Thermoluminescent dosimeters were used to determine the neutron and gamma-ray dose rates in the pile. Gamma-ray dose rate measurements have also been made in the air outside of the pile, while the radium-beryllium neutron source was being withdrawn from the pile. The Monte Carlo code has been used to calculate the coupled neutron-photon transport. Measured dose rates at various locations agreed with the calculated values within 5% to 15%.
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