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Abstract Attenuation of fission neutron has been studied in blocks of graphite at different locations. Fast, thermal and epithermal neutrons arising from the Cf-252 source at different locations within blocks of graphite of different dimensions were determined. The fast components were obtained using LR-115 track detector, covered with (n,x) radiator and Cd-foil, respectively. Some interesting physical parameters were thus deduced. They comprise the flux of fast, the thermal and epithermal neutrons, the build-up factor, the dosage and dose rate. |