Neutron personal dosimetry using polyallyl diglycol carbonate (PADC): Current status, best practices and proposed research

Bolzonella, M.; Ambrožová, Iva; Caresana, M.; Gibbens, N.; Gilvin, P. J.; Mariotti, Francesca; Savary, A.; Stabilini, Alberto; Vittoria, Fabio A.; Yukihara, E.G.; Chevallier, M.-A.

doi:10.1016/j.physo.2022.100114

Cited by 11 publications

(4 citation statements)

References 58 publications

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“…Those geometries are depicted in the upper part of Fig 1 . Within the voxels are MgB 4 O 7 doped with 0.5% Dy 3+ (2.56 g/cm 3 ) phosphor powders dispersed by PTFE (C 2 F 4 , 2.2 g/cm 3 ) [21]. The film is attached to human phantom, which is block in shape and consists of two layers: the outer one signifies clothing made from polyethyl terephthalate (PET, C 10 H 8 O 4 , 1.37 g/cm 3 ) and the inner one represents human body in its elemental composition (ICRP Publication 123, 2013) [22]. All elements are assumed to be in their natural abundances.…”

Section: Methodsmentioning

confidence: 99%

“…This dosimeter could detect the minimum neutron energy of 100 keV without a neutron converter. Some factors can affect the neutron sensitivity such as the material quality, chemical etching, and the features of the reading system adopted for track analysis [3]. Meanwhile, luminescence dosimeters make use of lithium-6 or boron-10 isotopes which undergo fission from neutron capture.…”

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Simulation on PTFE-Bound MgB4O7:Dy Film for Neutron Dosimetry

Prastowo,

Isnaini,

Abdurrosyid

et al. 2024

Preprint

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Magnesium borate (MgB4O7) is currently being studied as the material for neutron dosimetry. To become a proper dosimeter, magnesium borate is doped with dysprosium as the activator and PTFE (polytetrafluoroethylene) is used as the binder. To estimate the response of PTFE-bound MgB4O7:Dy for neutron dosimetry, Monte Carlo simulation was conducted by PHITS (Particle and Heavy Ion Transport Code System) software. The simulation consisted of dosimeter film of said materials attached to a simplified human phantom. The amount of PTFE ranged from 50% to 90% and the thickness of the film was varied from 0.5 mm to 2.5 mm. The result showed that this film dosimeter had high response to thermal neutrons and low response to fast neutrons, in contrast with the response of human body. Furthermore, it also suggested that the sample with the highest MgB4O7 content had the lowest absorbed dose due to self-shielding effect while on the thicker film, the effect of self-shielding also reduced the sensitivity of this film dosimeter.

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Section: Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation on PTFE-Bound MgB4O7:Dy Film for Neutron Dosimetry

Prastowo,

Isnaini,

Abdurrosyid

et al. 2024

Preprint

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“…In this study, we employ PADC detectors for slow neutrons through an n-alpha process. PADC is widely used for personal neutron dosimetry [3][4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Characterization of tracks from alpha-particles in PADC detectors for passive environmental monitoring of fast neutron radiation field

Biordi,

Sarchiapone,

Gallo

2024

J. Phys. D: Appl. Phys.

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Fast neutron dosimetry is particularly crucial in the realm of radioprotection, as it significantly contributes to evaluating the radiation protection measures. This assessment aims to ensure and enhance the effectiveness of implemented safeguards and precautions, thereby minimizing the risks and potential harm associated with radiation exposure. Given the substantial biological damage that fast neutrons can inflict when interacting with living tissues, accurate dosimetry is indispensable for ensuring the safety of personnel in these environments and for optimizing radiation therapy treatments. Employing an indirect detector technique, this research focuses on characterizing the geometrical and optical properties of tracks produced by alpha particles resulting from Neutron-Boron reactions and distinguish them from the background made up of tracks generated from radon decay and impurities on the surface of the detector. Through the development of a robust protocol for fast neutron dosimetry, we can not only differentiate between tracks produced by alpha particles of varying energy levels but also precisely quantify the dose resulting from exposure to the neutron field.A solid-state nuclear track detector (SSNTD) system (Politrack, Mi.am, Italy) was used to address the critical need for measuring exposure to fast neutrons.This advancement facilitates the implementation of more effective radioprotection strategies and contributes to the overall safety of radiation therapy procedures.

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“…The ever-challenging issue of neutron dosimetry is discussed in two papers, by Bolzonella et al (2022) and by Gómez-Ros et al (2023). The former discuss the fundamentals and current best practices while the latter illustrate new directions using a wide variety of dosimetry techniques.…”

mentioning

confidence: 99%