Neutron Spectra, Radiological Quantities and Instrument and Dosemeter Responses at a Magnox Reactor and a Fuel Reprocessing Installation

Measurements of the energy spectra and angle distributions have been carried out at five locations in a fuel reprocessing installation and at two locations at a Magnox reactor. The energy spectral distributions were determined using multispheres with either passive or active thermal neutron detection. Directional information was derived from the response of personal dosemeters mounted on phantoms. These evaluations enabled the estimation for the seven locations of the energy and angle weighted values of HE,H'(10) and personal dosemeter response, as well as of the isotropic quantity H*(10) and of the responses of NM2 and 0949 type rem meters. The results are analysed and discussed in terms of the relationships between primary and operational quantities, and between primary quantities and instrument and dosemeter responses. It is concluded that, in general, the operational quantity HP(10) will give a reasonable estimate of HE, and that a PADC etched track personal dosemeter measuring thermal, epithermal and fast neutrons is suitable for use in the neutron radiation fields surveyed. Some estimates of the proposed new quantity, effective dose, are included.