Nuclear Technology and Radiation Protection 2015 Volume 30, Issue 3, Pages: 175-187
https://doi.org/10.2298/NTRP1503175P
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Development and dosimetric characterization of indigenous PADC for personnel neutron dosimetry
Pal Rupali (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Nadkarni Vishnu S. (Goa University, Department of Chemistry, Taleigao Plateau, Goa, India)
Naik Diptesh (Goa University, Department of Chemistry, Taleigao Plateau, Goa, India)
Beck Mudit (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Bakshi Ashok Kumar (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Chougaonkar Mohan Pundarinath (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Chourasiya Ghanshyam (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Mayya Yelia Shankaranarayana (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
Babu Devu Appala Raju (Bhabha Atomic Research Centre, Radiological Physics & Advisory Division, Mumbai, India)
CR-39 is a solid state nuclear track detector, chemically known as
poly-allyl-diglycol-carbonate, widely used for personnel neutron monitoring
because of its sensitivity to neutrons, excellent optical properties that
facilitate the analysis and sufficiently long shelf life. Presently, this
detector is imported and is being used for the personnel neutron monitoring
programme in India. Hence, an effort was made towards the indigenous
development of these detectors. Different chemical processes for the
indigenous development of the poly-allyl-diglycol-carbonate detector, such as
the synthesis of allyl-diglycol-carbonate monomer and
isopropyl-peroxydicarbonate as initiators for the polymerization process,
were carried out and are reported in this paper. A method for casting
unbroken poly-allyl-diglycol-carbonate sheets sized 25 cm x 15 cm and of a
thickness between 500 µm and 800µm was developed. A longer polymerization
process also helps to increase neutron sensitivity, reduce the minimum
detection limit and increase the signal-to-noise ratio of the detector. The
study suggests that it is possible to develop indigenous
poly-allyl-diglycol-carbonate detectors with a minimum detection limit of 0.1
mSv and signal-to-noise ratio of 8.0.
Keywords: poly-allyl-diglycol-carbonate, electrochemical etching, neutron dosimetry