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Measurement of the neutron capture cross section of {sup 236}U

Conference ·
OSTI ID:22040593
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  1. CEA/Saclay, DSM/DAPNIA, Gif-sur-Yvette (France)
  2. CEC-JRC-IRMM, Geel (Belgium)
  3. Joint Inst. for Nuclear Research, Frank Laboratory of Neutron Physics, Dabna (Russian Federation)
  4. Inst. of Physics and Power Engineering, Kaluga region, Obninsk (Russian Federation)
  5. Oak Ridge National Laboratory, Physics Div., Oak Ridge (United States)
  6. Universidade de Santiago de Compostela (Spain)
  7. Istituto Nazionale di Fisica Nudeare, Trieste (Italy)
  8. Centro de Investigaciones Energeticas Medioambientales y Technologicas, Madrid (Spain)
  9. Univ. of Lodz, Lodz (Poland)
  10. Univ. of Ioannina (Greece)
+ Show Author Affiliations
In this paper we describe the {sup 236}U(n, {gamma}) reaction cross section measurement at the GELINA white pulsed neutron source of the Inst. 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 C{sub 6}D6-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 {sup 10}B 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 R-matrix resonance parameters is planned for the near future. (authors)
Research Organization:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
22040593
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BORON 10
COMPUTERIZED SIMULATION
CROSS SECTIONS
GAMMA RADIATION
KEV RANGE
LIQUID SCINTILLATION DETECTORS
MONTE CARLO METHOD
NEUTRON BEAMS
NEUTRON DETECTORS
NEUTRON FLUX
NEUTRON REACTIONS
NEUTRON SOURCES
PULSES
R MATRIX
TIME-OF-FLIGHT METHOD
URANIUM 236 TARGET
WEIGHTING FUNCTIONS