Abstract
The neutron capture cross section of 236U was measured in the neutron energy range from 1 eV to 10 keV by the neutron time‐of‐flight method at the GELINA white pulsed neutron source of the Institute for Reference Materials and Measurements (IRMM) in Geel (Belgium). The gamma rays originating from neutron capture events were detected by two C6D6‐based liquid scintillators using the pulse height weighting technique. The weighting function has been derived from Monte‐Carlo simulations of the detector response to monoenergetic gamma rays.The sample under investigation with a total amount of 338 mg of 236U was located in the neutron beam at a distance of 28.6 m from the source. The shape of the neutron flux was determined by a 10B neutron counter, placed approximately 60 cm upstream in the neutron beam line.The neutron capture yield in the resolved resonance region up to 1 keV has been derived from time‐of‐flight spectra.
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