Abstract

Neutron capture cross section measurements have been performed at the time-of-flight facility GELINA of the EC-JRC-Geel. Prompt gamma rays, originating from a natural silver sample, were detected by a pair of C6 D6 liquid scintillation detectors. The total energy detection principle in combination with the pulse height weighting technique has been used. In this contribution the experimental details together with the data reduction process are described. In addition, first results of calculations with REFIT are presented to verify the quality of recommended cross section data in the resolved resonance region.

Highlights

  • Natural silver is often used in an alloy together with cadmium and indium to produce control rods for water moderated power reactors

  • An evaluation of the resonance parameters for cadmium isotopes was performed by Volev et al [1]

  • This evaluation, which was strongly based on results of experiment at the GELINA (Geel LINear Accelerator [2]) facility of EC-JRC-Geel, was included in the JEFF3.2 neutron library

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Summary

Introduction

Natural silver (composed of 107Ag and 109Ag) is often used in an alloy together with cadmium and indium to produce control rods for water moderated power reactors Such an alloy, referred to as AIC, provides good mechanical properties and results in an uniform absorption spectrum. An evaluation of the resonance parameters for cadmium isotopes was performed by Volev et al [1] This evaluation, which was strongly based on results of experiment at the GELINA (Geel LINear Accelerator [2]) facility of EC-JRC-Geel, was included in the JEFF3.2 neutron library. In this contribution experiments to improve the nuclear data for 107Ag and 109Ag are described. This should result in a better prediction of the reactivity worth of AIC control rods

Experiment
Data reduction and analysis
Background correction for the flux response
Background correction for C6D6 response
Resonance analysis with REFIT
Findings
Conclusions

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