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Measurements of thermal and fast neutron fluxes in a mixed radiation field have been carried out by etching technique applied to fission tracks on a mica detector. As fissionable material, use was made of electrochemical deposits-on Au-coated Cu-plate or stainless steel plate-of 232Th, 231Pa, natural U, depleted U, 232U, 237Np, 238Pu and 239Pu. The atomic density of the fissionable material on the plate was measured by α-spedrometry. These plates were placed in contact with muscovite mica, and exposed to neutron flux in a TRIGA Mark-II nuclear reactor, both with and without thermal neutron absorber of Cd. After the irradiation, the mica was etched by hydrofluoric acid solution, and the track density counted on a microphotograph. The values of the thermal and fast neutron fluxes were obtained from the mean cross-section of the fission reactions undergone by the different nuclides present. The resulting flux values showed reasonably good agreement with the values obtained by other methods. A discussion is given on the nuclear data obtained for several nuclides. A proposal is presented also on a simple and practical method for determining high track density by photometer with dark-field illumination.

Measurement of Neutron Flux in Nuclear Reactor by means of Fission Track Method