R-Matrix Analysis of the ²³⁶U(n,gamma) Reaction in theResolved Resonance Energy Region

Conference · Fri Feb 01 00:00:00 EST 2008

OSTI ID:958933

Mezentseva, Zh. ^[1]; Koehler, Paul Edward ^[2]; Collaboration, n_TOF ^[3]

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1. French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette
2. ORNL
3. Collaboration affiliations

The neutron capture cross section of 236U 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 C6D6-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 236U 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 10B 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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 958933
• Resource Relation: Conference: 13th Symposium on Capture Gamma Ray Spectroscopy and Related Topics - Cologne, , Germany - 8/24/2008 12:00:00 AM-8/29/2008 12:00:00 AM
• Country of Publication: United States
• Language: English

Related Subjects

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
CAPTURE
CROSS SECTIONS
ENERGY RANGE
LIQUID SCINTILLATORS
NEUTRON BEAMS
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON SOURCES
NEUTRONS
R MATRIX
RESONANCE
SHAPE
SPECTRA
SPECTROSCOPY
TIME-OF-FLIGHT METHOD
WEIGHTING FUNCTIONS