gamma detection - FNDA 2011

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Fast neutron inelastic scattering at the nELBE facility 235 U Fission chamber efficiency � calculation from ENDF (n,fis) cross section � simulation with MCNP (includes multiple processes and beam attenuation) � incredients • number of fissionable nuclei • fission <strong>detection</strong> efficiency • homogeneity Seite 45 Nolte, Nucl.Sci.Eng.156(2007)197 Gayther, Metrologia 27 (1990) 221
Fast neutron inelastic scattering at the nELBE facility The 56 Fe(n,n’γ) cross section for the 1 st excited state Seite 46 � absolute normalization still missing Uncertainties: @ 2 MeV Fission chamber efficiency 2.1 % Fission chamber counts 1.5 % Fission chamber background 1.8 % Loss due to ADC range 0.1 % Scaling factor FCTarget 0.3 % Attenuation factor 1.1 % � Neutron flux 2.9 % Sample in counts 2.3 % Sample out counts 15.9 % Normalization factor 1.5 % BaF 2 efficiency 1.3 % Plastic efficiency 2.2 % � Reaction rate 3.8 % � Cross section 4.8 %
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gamma detection - FNDA 2011

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