Radiation Protection Dosimetry Vol. 110 Nos. 1-4 © Oxford University Press 2004; all rights reserved
Practical implications of neutron survey instrument performance
1 National Radiological Protection Board, Chilton, Didcot, Oxon OX11 0RQ, UK
2 National Physical Laboratory, Teddington, Middlesex TW11 0LW, UK
* Corresponding author: rick.tanner{at}nrpb.org.
Improvements have been made to the Monte Carlo modelling used to calculate the response of the neutron survey instruments most commonly used in the UK, for neutron energies up to 20 MeV. The improved modelling of the devices includes the electronics and battery pack, allowing better calculations of both the energy and angle dependence of response. These data are used to calculate the response of the instruments in rotationally and fully isotropic, as well as unidirectional fields. Experimental measurements with radionuclide sources and monoenergetic neutron fields have been, and continue to be made, to test the calculated response characteristics. The enhancements to the calculations have involved simulation of the sensitivity of the response to variations in instrument manufacture, and will include the influence of the user and floor during measurements. The practical implications of the energy and angle dependence of response, variations in manufacture, and the influence of the user are assessed by folding the response characteristics with workplace energy and direction distributions.
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