Abstract
An activation facility has been designed for the accomodation and safe-handling of up to 50 mg of 252Cf neutron source. The absolute values of thermal, epithermal and fast neutron fluxes were determined by the foil activation method using In, Dy, Au, Al and Fe detectors, and compared with other experimental results and theoretical estimations. The Maxwellian temperature and average energy of 252Cf neutron spectrum have been determined.
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