Abstract

Radiation transport calculations provide the backbone for the spectrum characterization used to support experimenters at research reactors. The radiation transport calculations provide a priori neutron spectra used in least squares spectrum adjustment. In addition, calculations are often the sole source of baseline neutron spectra data when an experimental test object substantially perturbs the free-field spectrum. It is crucial that analysts provide high fidelity uncertainty quantification for the spectrum calculations. This is an investigation of systematic trends as the distance to the source is varied in calculated spectra at a fast burst facility. A comparison of ratios is designed to highlight trends in the C/E ratios that may shed light on deficiencies in the transport cross sections or sensitivities to the details of the facility modeling. Initial comparisons of the latest IRDF-2002 [1] dosimetry cross section library to the SNL RML [2] cross section library have been made and are discussed.

Issue Section:
Research Papers
Keywords:
neutron spectra, monte carlo, cross section, spectrum adjustment, transport cross section

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