Effective Fission Cross Sections and Neutron Spectra in an NRX Type Uranium Metal Rod

C. B. Bigham; S. A. Kushneriuk; P. R. Tunnicliffe

doi:dx.doi.org/10.13182/NSE63-A26533

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Effective Fission Cross Sections and Neutron Spectra in an NRX Type Uranium Metal Rod

C. B. Bigham, S. A. Kushneriuk, P. R. Tunnicliffe

Nuclear Science and Engineering / Volume 16 / Number 3 / July 1963 / Pages 299-314

Technical Paper / dx.doi.org/10.13182/NSE63-A26533

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Fission cross section ratios of U²³³, U²³⁵, and Pu²³⁹ and capture rates in Mn⁵⁵ and In¹¹⁵ have been measured in an NRX type uranium metal rod irradiated in a heavy water moderated reactor. The results have been compared to the values obtained using a model designed for NRX burnup calculations. Agreement was obtained using an “incurrent” spectrum composed of a Maxwellian thermal component and an epithermal component of the form obtained from neutron spectrometer measurements. Changes in spectrum caused by the light water coolant were also studied.