In this paper we describe the 236U(n,gamma) neutron capture cross section mea¨surement at the GELINA white pulsed neutron source of the Institute for Reference Materials and Measurements (IRMM) in Geel. The sample was placed in the neutron beam at the flight station located at a nominal distance of 30 m from the neutron source. Neutron capture gamma-rays were detectedby two C6D6 based liquid scintillator gamma-ray detectors as a function of theneutron time-of-flight using the pulse height weighting technique. The pulseheight weighting function has been derived from Monte Carlo simulations ofthe detector response to mono-energetic gamma rays. The shape of the neu¨tron flux was measured with a 108 chamber, placed about 50 cm upstream in the neutron beam. The capture yield in the resolved resonance region up to 3 keV has been derived and will be presented here. The analysis of the capture yield in terms of R-matrix resonance. parameters is planned far the near future.

Measurement of the Neutron Capture Cross Section of 236U

Ventura, A.;
2006-09-10

Abstract

In this paper we describe the 236U(n,gamma) neutron capture cross section mea¨surement at the GELINA white pulsed neutron source of the Institute for Reference Materials and Measurements (IRMM) in Geel. The sample was placed in the neutron beam at the flight station located at a nominal distance of 30 m from the neutron source. Neutron capture gamma-rays were detectedby two C6D6 based liquid scintillator gamma-ray detectors as a function of theneutron time-of-flight using the pulse height weighting technique. The pulseheight weighting function has been derived from Monte Carlo simulations ofthe detector response to mono-energetic gamma rays. The shape of the neu¨tron flux was measured with a 108 chamber, placed about 50 cm upstream in the neutron beam. The capture yield in the resolved resonance region up to 3 keV has been derived and will be presented here. The analysis of the capture yield in terms of R-matrix resonance. parameters is planned far the near future.
10-set-2006
Applicazioni di fisica e tecnologie nucleari
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5696
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