Journal of Medical Physics
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ORIGINAL ARTICLE
Year : 2014  |  Volume : 39  |  Issue : 4  |  Page : 225-230

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


1 Health Physics Division, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India
2 Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India
3 Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai, Maharashtra, India

Correspondence Address:
S P Tripathy
Room No. 510, CT and CRS Building, AERB Complex, Anushaktinagar, Mumbai 400 094, Maharashtra
India
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Source of Support: None, Conflict of Interest: None


DOI: 10.4103/0971-6203.144487

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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 9 Be (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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