LET spectrometry of 14MeV (D–T) neutrons using CR-39 track detectors

Sahoo, G.S.; Tripathy, S.P.; Sunil, C.; Sarkar, P. K.

doi:10.1016/j.nima.2013.01.007

Cited by 14 publications

(3 citation statements)

References 28 publications

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“…The accelerator neutron source used the deuterium and tritium reactions to generate monoenergetic neutrons. The reaction formula is as follows [5]:…”

Section: Introductionmentioning

confidence: 99%

Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Wang

Zhao

et al. 2020

J. Inst.

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A: A neutron yield monitoring system based on a 10 BF 3 tube array was designed to monitor fast neutrons with an energy of 14 MeV and a yield of 10 4 -10 8 produced by a deuterium-tritium fusion reaction. The array contained six 10 BF 3 tubes of different sizes. The signal readout system used a charge sensitive preamplifier (CSA) as the front-end circuit. The CSA was optimized and tested to ensure that it met the measurement requirements for low charge and high counting rate. The zero-capacitance equivalent noise charge (ENC) was 2425 e − and the ENC slope was 15 e − /pF. In the temperature range 0-60 • C, the ENC slope was 10 e − / • C and the baseline drift was less than 0.05 mV/ • C. In the 10 h long-term stability test, the baseline drift was less than 0.07 mV.

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“…The accelerator neutron source used the deuterium and tritium reactions to generate monoenergetic neutrons. The reaction formula is as follows [5]:…”

Section: Introductionmentioning

confidence: 99%

Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Wang

Zhao

et al. 2020

J. Inst.

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“…These are routinely used for area as well as personnel monitoring in the complex radiation environment of particle accelerators [3][4][5][6], where the field can be often pulsed, mixed and the neutron spectrum can go up to hundreds of MeV. The basic principle for neutron detection with these detectors is that the neutron-induced recoil tracks (proton, carbon and oxygen) are usually developed to microscopic level by some of the etching techniques [7,8] and the tracks are counted to determine the neutron dose based on the established calibration curves [9,10] or the LET spectrum is generated from the track parameters to estimate the dose [11][12][13]. An attempt is made in this study to explore an alternate approach for neutron dose estimation without involving the tedious track counting procedure with optical microscope.…”

Section: Introductionmentioning

confidence: 99%

Effect of 14 MeV neutrons on the optical properties of CR-39 detector

Sahoo

Tripathy

Jena

et al. 2014

Eur. Phys. J. Appl. Phys.

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This study is carried out to establish a correlation between optical absorbance and track density in CR-39 detectors exposed to different fluences of D-T (14 MeV) neutrons. This can be useful in estimating the neutron fluence and hence the dose without involving the tedious track counting procedure, especially when the track density is extremely high. Variation in the optical properties is studied using UV-VIS-NIR (ultraviolet-visible-near infrared) spectroscopic technique. The neutron-induced recoil tracks are developed by chemical etching and the track density is determined. The optical transmission spectra are obtained for pristine and neutron irradiated detectors before and after etching. A linear relationship is obtained between the track density and the optical absorbance with increasing neutron fluence. Another objective of this work is to study the effect of etching on the optical properties such as transmittance and absorbance of irradiated CR-39 detectors. The optical properties are found to be changing due to the development of tracks in the detector.

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“…[ 17 ] Each method has its inherent advantages and limitations, but can always serve as complementing to other methods if any of the techniques fail under typical radiation environments. LET spectrometry method using CR-39 detectors[ 18 19 ] is also another way of estimating neutron dose, which is useful in situations when the information about neutron energy distribution and the radiation components are not available. In this approach, the discrimination of different radiation components (such as proton, carbon and oxygen) due to neutron interaction in CR-39 is not required.…”

Section: Introductionmentioning

confidence: 99%

Neutron dose estimation via LET spectrometry using CR-39 detector for the reaction ⁹ Be (p, n)

et al. 2014

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CR-39 detectors, widely used for neutron dosimetry in accelerator radiation environment, have also been applied in tissue microdosimetry by generating the linear energy transfer (LET) spectrum. In this work, the neutron dose has been estimated via LET spectrometry for 9Be (p, n) reaction which is useful for personnel monitoring around particle accelerators and accelerator based therapy facilities. Neutrons were generated by the interaction of protons of 6 different energies from 4–24 MeV with a thick Be target. The LET spectra were obtained from the major and minor radii of each track and the thickness of removed surface. From the LET spectra, the absorbed dose (DLET) and the dose equivalent (HLET) were estimated using Q-L relationship as given by International Commission on Radiological Protection (ICRP) 60. The track density in CR-39 detector and hence the neutron yield was found to be increasing with the increase in projectile (proton) energy. Similar observations were also obtained for absorbed dose (DLET) and dose equivalents (HLET).

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LET spectrometry of 14MeV (D–T) neutrons using CR-39 track detectors

Cited by 14 publications

References 28 publications

Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Effect of 14 MeV neutrons on the optical properties of CR-39 detector

Neutron dose estimation via LET spectrometry using CR-39 detector for the reaction ⁹ Be (p, n)

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LET spectrometry of 14MeV (D–T) neutrons using CR-39 track detectors

Cited by 14 publications

References 28 publications

Design and performance of the front-end electronics for a 10BF3 tube array

Design and performance of the front-end electronics for a 10BF3 tube array

Effect of 14 MeV neutrons on the optical properties of CR-39 detector

Neutron dose estimation via LET spectrometry using CR-39 detector for the reaction 9 Be (p, n)

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Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Design and performance of the front-end electronics for a ¹⁰BF₃ tube array

Neutron dose estimation via LET spectrometry using CR-39 detector for the reaction ⁹ Be (p, n)