Measurement of the Neutron Capture Cross Section of 236U
In this paper we describe the 236U(n,gamma) reaction cross section measurement 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 a flight station located at a nominal distance of 30 m from the neutron
source. Neutron capture gamma rays were detected by two C6D6-based liquid
scintillator gamma-ray detectors as a function of the neutron time-of-flight
using the pulse height weighting technique. The pulse height weighting function
has been derived from Monte Carlo simulations of the detector response
to mono-energetic gamma rays. The shape of the neutron flux was measured
with a 10B chamber, placed about 60 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 Rmatrix
resonance parameters is planned for the near future.
GUNSING Frank;
SCHILLEBEECKX Peter;
WYNANTS Ruud;
PLOMPEN Arjan;
RULLHUSEN Peter;
N_TOF COLLABORATION The;
2007-01-29
American Nuclear Society
JRC36232
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