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gamma detection - FNDA 2011

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Fast neutron inelastic scattering at the nELBE facility<br />

Determination of the inelastic scattering cross section<br />

� Incoming Neutron Flux<br />

Seite 62<br />

• 235 U fission chamber neutron <strong>detection</strong> efficiency � calculation/simulation<br />

- number of fissionable nuclei<br />

- fission <strong>detection</strong> efficiency<br />

- homogeneity<br />

• count rate in time of flight spectrum � statistics + background subtraction<br />

• corrections for loss due to ADC gate<br />

• scaling factor for ratio of beam area at fission chamber and sample size<br />

• corrections for flux attenuation inside fission chamber, air and sample<br />

fission chamber neutron beam sample

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