Abstract

BackgroundPhoto-neutrons are produced at the head of the medical linear accelerators (linac) by the interaction of high-energy photons, and patients receive a whole-body-absorbed dose from these neutrons. The current study aimed to find an efficient shielding material for fast neutrons.MethodsNanoparticles (NPs) of Fe3O4 and B4C were applied in a matrix of silicone resin to design a proper shield against fast neutrons produced by the 18 MeV photon beam of a Varian 2100 C/D linac. Neutron macroscopic cross-sections for three types of samples were calculated by the Monte Carlo (MC) method and experimentally measured for neutrons of an Am-Be source. The designed shields in different concentrations were tested by MCNPX MC code, and the proper concentration was chosen for the experimental test. A shield was designed with two layers, including nano-iron oxide and a layer of nano-boron carbide for eliminating fast neutrons.ResultsMC simulation results with uncertainty less than 1% showed that for discrete energies and 50% nanomaterial concentration, the macroscopic cross-sections for iron oxide and boron carbide at the energy of 1 MeV were 0.36 cm− 1 and 0.32 cm− 1, respectively. For 30% nanomaterial concentration, the calculated macroscopic cross-sections for iron oxide and boron carbide shields for Am-Be spectrum equaled 0.12 cm− 1 and 0.15 cm− 1, respectively, while they are 0.15 cm− 1 and 0.18 cm− 1 for the linac spectrum. In the experiment with the Am-Be spectrum, the macroscopic cross-sections for 30% nanomaterial concentration were 0.17 ± 0.01 cm− 1 for iron oxide and 0.21 ± 0.02 cm− 1 for boron carbide. The measured transmission factors for 30% nanomaterial concentration with the Am-Be spectrum were 0.71 ± 0.01, 0.66 ± 0.02, and 0.62 ± 0.01 for the iron oxide, boron carbide, and double-layer shields, respectively. In addition, these values were 0.74, 0.69, and 0.67, respectively, for MC simulation for the linac spectrum at the same concentration and thickness of 2 cm.ConclusionResults achieved from MC simulation and experimental tests were in a satisfactory agreement. The difference between MC and measurements was in the range of 10%. Our results demonstrated that the designed double-layer shield has a superior macroscopic cross-section compared with two single-layer nanoshields and more efficiently eliminates fast photo-neutrons.

Highlights

  • Application of external photon beam radiation therapy with the energy greater than 10 MeV produces unwanted photo-neutrons

  • In radiotherapy with megavoltage photon beams the risk of secondary primary cancer increases in out-offield organs due to the stray dose caused by the photons scattered from the treatment head, photons leakage through treatment head components, photo-neutrons produced in the treatment head, and photons scattered within the patient [8,9,10,11]

  • Experimental measurements and Monte Carlo (MC) calculations uncertainties The main sources of experimental uncertainties included limited accuracy of the BF3 detector, uncontrolled changes to the environment and conditions, limitations, and simplifications of the experimental procedure

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Summary

Introduction

Application of external photon beam radiation therapy with the energy greater than 10 MeV produces unwanted photo-neutrons. Neutron-absorbing materials have been utilized as barriers in maze and treatment room walls, examples of which include concrete and borated polyethylene in the doors of treatment rooms [4,5,6]. These barriers must be of sufficient thickness to protect radiation workers in radiation therapy installations [7]. The current study aimed to find an efficient shielding material for fast neutrons

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