BARC/PUB/2015/0466

 
 

Selection of Neutron-absorbing materials to improve the low-energy response of a Zr-based extended neutron monitor using Monte Carlo simulations

 
     
 
Author(s)

Biju, K.; Sunil, C.; Tripathy, S. P.; Joshi, D. S.; Bandyopadhyay, T.; Sarkar, P. K.
(HPD)

Source

Radiation Protection Dosimetry, 2015. Vol. 163 (2): pp. 160-165

ABSTRACT

Monte Carlo simulations have been carried out using the FLUKA code to improve the neutron ambient dose equivalent [H*(10)] response of the ZReC (zirconium-lined portable neutron counter responding satisfactorily to neutrons up to 1 GeV) by introducing various neutron absorbers in the system such as cadmium, gadolinium, natural boron, enriched 10B and borated polythene. It was found that ZReC can be effectively used as a portable neutron monitor by introducing any one of the following perforated layers: 5 mm thick natural boron, 0.5 mm thick enriched 10B or 1 cm high-density polythene mixed with 50 % boron by weight. The integral response of the instrument was also calculated for some typical reference neutron fields. The relative ambient dose equivalent response of the said system is also found comparable with that of the existing LINUS neutron monitor.

 
 
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