B LEAL1
, F. CASTILLO2†, J GUTIERREZ1
, JI GOLZARRI3
, I GAMBOADEBUEN1
, G. ESPINOSA3 H MARTÍNEZ2
1 Instituto de Ciencias Nucleares, Universidad Nacional Autónoma de México,
Apartado Postal 70-543, 04510, Ciudad Universitaria, México D. F., México
2 Laboratorio de Espectroscopia, Instituto de Ciencias Físicas, Universidad Nacional
Autónoma de México, Apartado Postal 48-3, 62251, Cuernavaca Morelos, México
3 Instituto de Física, Universidad Nacional Autónoma de México, Apartado Postal 20-
364, 01000, Ciudad de México, México
Abstract A linear electron accelerator for medical use is a device for
the treatment of tumors by collimated beams of electrons and/or photons.
These accelerators are devices that employ electromagnetic waves of high
frequency, to accelerate electrons that are used directly in the treatment
of superficial tumors, or, if they are made to hit them on an appropriate
target, they can produce photons of high energy destined to the treatment
of deeptumors.Depending on the energy of the electrons and photons and
the materials that make up the head of the accelerator and the target, this
equipment will produce in addition to the aforementioned radiation, neutron
fields of regular intensity. It is necessary to estimate the equivalent dose
due to the neutrons themselves, the doses due to the gamma field of neutron
capture, produced by the capture of thermal neutrons in the concrete of the
bunker, and the gamma doses due to phenomena of neutron activation of
elements of the own accelerator.
It is therefore important to be able to measure (detect, quantify, dose, etc.) both
photons and neutrons in these cases and others more. In this work we use three
different detectors, namely a scintillator-photomultiplier system, a fast reading
dosimeter and bubble detector. The idea is to measure the radiation separately
and compare their results. The results obtained were the mixed gamma-neutron field spectrum, the dose
due only to neutrons obtained by the bubble detectors, which is compared to
the dose obtained by the second fast reading dosimeters (model 884), plus the
dose obtained by the first dosimeters (model 609) and finally the dose obtained
by the Victoreen dosimeter.
DOI:
https://doi.org/10.15415/jnp.2017.51021
LINK:
http://dspace.chitkara.edu.in/jspui/bitstream/1/881/1/51021_JNP_Castelo.pdf