Simulation study of the dose and energy responses of FNTD personal neutron dosimetry
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The objective of this work was to use the Geant4 toolkit to perform simulation studies on the personal dose response of fluorescent nuclear track detectors (FNTDs). The entire structure of the FNTD response can be designed, and the detector’s energy and dose responses can be optimized in a broad energy range (0.01 eV–20 MeV). In general, the detectors used 6LiF and CH2 converters that have high energy and high dose response at neutron energies lower than 10 eV and greater than 1 MeV, respectively. The method of least squares was used to optimize the dose response of H*(10) and the energy response corresponding to Rtotal. The values of the optimized response of H*(10) lie between 0.8 and 1.4, corresponding to the energy ranges 0.01 eV–70 keV and 4–14 MeV, respectively. This occupies nearly eight out of the nine orders of the total energy range. Even though the optimized response of Rtotal is constrained between 0.89 and 1.1 in the energy range of 0.01 eV–20 MeV, it is suitable for obtaining the broad neutron spectrum of fluence with good accuracy.
KeywordsFNTD Geant4 Al2O3/C, Mg Personal neutron dose
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