R-matrix analysis of the {sup 236}U(n,{gamma}) reaction in the resolved resonance energy region
Journal Article
·
· AIP Conference Proceedings
- CEA/Saclay-DSM/IRFU/SPhN, Gif-sur-Yvette (France)
- CEC-JRC-IRMM, Geel (Belgium)
- CERN, Geneva (Switzerland)
- Joint Institute for Nuclear Research, Frank Laboratory of Neutron Physics, Dubna (Russian Federation)
- Institute of Physics and Power Engineering, Kaluga region, Obninsk (Russian Federation)
- International Atomic Energy Agency (IAEA), Nuclear Data Section, Vienna (Austria)
- Switzerland
The neutron capture cross section of {sup 236}U was measured in the neutron energy range from 1 eV to 10 keV by the neutron time-of-flight method at the GELINA white pulsed neutron source of the Institute for Reference Materials and Measurements (IRMM) in Geel (Belgium). The gamma rays originating from neutron capture events were detected by two C{sub 6}D{sub 6}-based liquid scintillators using the pulse height weighting technique. The weighting function has been derived from Monte-Carlo simulations of the detector response to monoenergetic gamma rays.The sample under investigation with a total amount of 338 mg of {sup 236}U was located in the neutron beam at a distance of 28.6 m from the source. The shape of the neutron flux was determined by a {sup 10}B neutron counter, placed approximately 60 cm upstream in the neutron beam line.The neutron capture yield in the resolved resonance region up to 1 keV has been derived from time-of-flight spectra.
- OSTI ID:
- 21255445
- Journal Information:
- AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1090; ISSN APCPCS; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BORON 10
CAPTURE
COMPUTERIZED SIMULATION
CROSS SECTIONS
EV RANGE
GAMMA RADIATION
GAMMA SPECTROSCOPY
KEV RANGE 01-10
LIQUID SCINTILLATORS
MONTE CARLO METHOD
NEUTRON BEAMS
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON SOURCES
NEUTRONS
R MATRIX
TIME-OF-FLIGHT METHOD
URANIUM 236
URANIUM 236 TARGET
WEIGHTING FUNCTIONS
BORON 10
CAPTURE
COMPUTERIZED SIMULATION
CROSS SECTIONS
EV RANGE
GAMMA RADIATION
GAMMA SPECTROSCOPY
KEV RANGE 01-10
LIQUID SCINTILLATORS
MONTE CARLO METHOD
NEUTRON BEAMS
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON SOURCES
NEUTRONS
R MATRIX
TIME-OF-FLIGHT METHOD
URANIUM 236
URANIUM 236 TARGET
WEIGHTING FUNCTIONS