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Experimental Determination of the Differential Fast-Neutron Flux in the High Flux Isotope Reactor Using Techniques Threshold Detectors

H. L. Dodds, Jr., P. F. Pasqua

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 296-301

Paper / Technique / dx.doi.org/10.13182/NT70-A28677

The differential fast-neutron flux above 0.5 MeV at one spatial position in the High Flux Isotope Reactor was determined experimentally using several threshold activation detectors. The series expansion technique utilizing the concept of least squares was used to obtain an approximate solution to the set of integral equations which are defined by the experimentally determined activation data. Good agreement was achieved between the integrated flux (i.e., the differential flux integrated above 0.5 MeV) determined in this work and the integrated flux determined independently using one-dimensional, multigroup diffusion theory.