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Radiation Protection Dosimetry 2004 110(1-4):207-211; doi:10.1093/rpd/nch128
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Radiation Protection Dosimetry Vol. 110 Nos. 1-4 © Oxford University Press 2004; all rights reserved

Improved neutron detection by gamma-ray spectroscopy

Z. B. Alfassi1,*, T. Zlatin1, O. Manor1, S. Dubinsky1 and U. German2

1 Ben Gurion University of the Negev, Beer Sheva, 84105, Israel
2 Nuclear Research Centre-Negev, Beer Sheva, 84190, Israel

* Corresponding author: alfassi{at}bgumail.bgu.ac.il

Most high-efficiency interactions for neutron detection are with thermal neutrons, and the detection of the prompt gamma radiation emitted as a result of thermal neutron absorption in specific materials was sometimes used. These materials are named converters, the most widespread being 10B, 113Cd or 73Ge (the last two materials are detector materials themselves for CdZnTe and HPGe detectors). However, for these materials, the main gamma-ray energies are relatively low (in the region 473–600 keV), and there are interferences from other gamma rays present in background. Different combinations of moderator–converter–detector systems were employed to optimise the system efficiency and signal-to-background ratio, using B, Cd, Gd and Cl converters and HPGe, NaI(Tl) and BGO detectors. When using a Cl converter, the 1164.7 keV peak seems to be a good choice when a HPGe spectrometer is used. A very practical material containing chlorine is PVC.


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