Neutron dosimetry using an electret albedo dosimeter

The method of albedo dosimetry can provide a measure of individual dose in stray neutron fields at nuclear power plants. Calculated and measured neutron sensitivities of a simple albedo dosimeter based on the utilization of the (n, alpha ) reaction on boron within the sensitive chamber volume of an electret ionization chamber are presented. It is noted that, for practical use in mixed neutron-gamma-fields, the area of the boron layer must be optimized in such a way that the sensitivities for photons and neutrons are equal to their effective dose equivalents. Then the total effective dose equivalent can be determined from the response of the ionization chamber.<
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