A Technique for Pulsed Neutron Generator Flux Evaluation

A technique is presented using a thick copper foil and utilizing the Cu63(n,2n) Cu62 reaction of copper for determining the flux from a pulsed neutron generator. The pulse neutron generator produces 14.2 MeV neutrons by the interaction of deuterium and tritium. The foil is activated, counted and the integrated flux in n/cm2 is calculated. Having a value of integrated flux at a given location, the integrated flux at any other point near the target can be deduced by using total flux distribution tables. These tables are available from White Sands Missile Range on request. These tables were prepared on the assumption that the source is a thin, planar, isotropic, radiating disk.