Monte Carlo Simulations of Neutron Ambient Dose Equivalent in a Novel Proton Therapy Facility Design.

Uwe Titt,Enzo Pera,Michael T Gillin

doi:10.14338/ijpt-19-00071.1

Abstract

Purpose:The neutron shielding properties of the concrete structures of a proposed proton therapy facility were evaluated with help of the Monte Carlo technique. The planned facility's design omits the typical maze-structured entrances to the treatment rooms to facilitate more efficient access and, instead, proposes the use of massive concrete/steel doors. Furthermore, straight conduits in the treatment room walls were used in the design of the facility, necessitating a detailed investigation of the neutron radiation outside the rooms to determine if the design can be applied without violating existing radiation protection regulations. This study was performed to investigate whether the operation of a proton therapy unit using such a facility design will be in compliance with radiation protection requirements.Methods:A detailed model of the planned proton therapy expansion project of the University of Texas, M. D. Anderson Cancer Center in Houston, Texas, was produced to simulate secondary neutron production from clinical proton beams using the MCNPX Monte Carlo radiation transport code. Neutron spectral fluences were collected at locations of interest and converted to ambient dose equivalents using an in-house code based on fluence to dose-conversion factors provided by the International Commission on Radiological Protection.Results and Conclusions:At all investigated locations of interest, the ambient dose equivalent values were below the occupational dose limits and the dose limits for individual members of the public. The impact of straight conduits was negligible because their location and orientation were such that no line of sight to the neutron sources (ie, the isocenter locations) was established. Finally, the treatment room doors were specially designed to provide spatial efficiency and, compared with traditional maze designs, showed that while it would be possible to achieve a lower neutron ambient dose equivalent with a maze, the increased spatial (and financial) requirements may offset this advantage.

Highlights

The erection of a new proton therapy facility warrants a thorough investigation of the shielding against unwanted exposure of workers and members of the public inside and outside the facility
The most efficient energy transfer takes place between neutrons and light nuclei, which makes concrete an efficient radiation barrier because of the its relatively high content of hydrogen and oxygen. Another possibility is that the neutrons undergo neutron-b-decay into a proton, an electron, and an electron-neutrino; the half-life of a free neutron is on the order of 10 minutes and, this channel is unlikely to play a significant role in the context of radiation protection in a proton therapy facility
This study describes the Monte Carlo simulations of secondary neutron dose in a newly planned proton therapy facility in Houston, Texas

Summary

Introduction

The erection of a new proton therapy facility warrants a thorough investigation of the shielding against unwanted exposure of workers and members of the public inside and outside the facility. Direct and indirect inelastic reactions of protons in any material lead to the emission of secondary neutrons (and to a lesser degree other charged particles, such as secondary protons, alphas, or heavier fragments of the target nuclei). The most efficient energy transfer takes place between neutrons and light nuclei, which makes concrete an efficient radiation barrier because of the its relatively high content of hydrogen and oxygen. Another possibility is that the neutrons undergo neutron-b-decay into a proton, an electron, and an electron-neutrino; the half-life of a free neutron is on the order of 10 minutes and, this channel is unlikely to play a significant role in the context of radiation protection in a proton therapy facility

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