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Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4

Abstract

Accurate and reliable neutron capture cross sections are needed in many research areas, including stellar nucleosynthesis, advanced nuclear fuel cycles, waste transmutation, and other applied programs. In particular, the accurate knowledge of U{sup 234}(n,{gamma}) reaction cross section is required for the design and realization of nuclear power plants based on the thorium fuel cycle. We have measured the neutron capture cross section of U{sup 234}, with a 4{pi} BaF{sub 2} Total Absorption Calorimeter, at the recently constructed neutron time-of-flight facility n-TOF at CERN in the energy range from 0.03 eV to 1 MeV. Monte-Carlo simulations with GEANT4 and MCNPX of the detector response have been performed. After the background subtraction and correction with dead time and pile-up, the capture yield from 0.03 eV up to 1.5 keV was derived. The analysis of the capture yield in terms of R-matrix resonance parameters is discussed. We have identified 123 resonances and measured the resonance parameters in the energy range from 0.03 eV to 1.5 keV. The mean radiative width <{gamma}{sub {gamma}}> is found to be (38.2 {+-} 1.5) meV and the mean spacing parameter <D{sub 0}> is (11.0 {+-} 0.2) eV, both values agree well with recommended values.
Authors:
Publication Date:
Nov 15, 2006
Product Type:
Thesis/Dissertation
Report Number:
FRNC-TH-7029
Resource Relation:
Other Information: TH: These physique nucleaire; 143 refs
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; COMPUTERIZED SIMULATION; DATA ANALYSIS; EXPERIMENTAL DATA; FOUR-PI DETECTORS; G CODES; GAMMA SPECTROSCOPY; INTEGRAL CROSS SECTIONS; LEVEL WIDTHS; M CODES; MONTE CARLO METHOD; NEUTRON REACTIONS; R MATRIX; S CODES; SCINTILLATION COUNTERS; TIME-OF-FLIGHT METHOD; URANIUM 234
OSTI ID:
20953810
Research Organizations:
Universite d'Evry Val d'Essonne, 91 - Evry (France)
Country of Origin:
France
Language:
French
Other Identifying Numbers:
TRN: FR0702018105122
Availability:
Available from INIS in electronic form
Submitting Site:
FRN
Size:
233 pages
Announcement Date:
Dec 27, 2007

Citation Formats

Dridi, W. Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4. France: N. p., 2006. Web.
Dridi, W. Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4. France.
Dridi, W. 2006. "Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4." France.
@misc{etde_20953810,
title = {Measurement of the neutron capture cross section of U{sup 234} in n-TOF at CERN for Generation IV nuclear reactors; Mesure de la section efficace de capture neutronique de l'{sup 234}U a n-TOF au CERN pour les reacteurs nucleaires de generation 4}
author = {Dridi, W}
abstractNote = {Accurate and reliable neutron capture cross sections are needed in many research areas, including stellar nucleosynthesis, advanced nuclear fuel cycles, waste transmutation, and other applied programs. In particular, the accurate knowledge of U{sup 234}(n,{gamma}) reaction cross section is required for the design and realization of nuclear power plants based on the thorium fuel cycle. We have measured the neutron capture cross section of U{sup 234}, with a 4{pi} BaF{sub 2} Total Absorption Calorimeter, at the recently constructed neutron time-of-flight facility n-TOF at CERN in the energy range from 0.03 eV to 1 MeV. Monte-Carlo simulations with GEANT4 and MCNPX of the detector response have been performed. After the background subtraction and correction with dead time and pile-up, the capture yield from 0.03 eV up to 1.5 keV was derived. The analysis of the capture yield in terms of R-matrix resonance parameters is discussed. We have identified 123 resonances and measured the resonance parameters in the energy range from 0.03 eV to 1.5 keV. The mean radiative width <{gamma}{sub {gamma}}> is found to be (38.2 {+-} 1.5) meV and the mean spacing parameter <D{sub 0}> is (11.0 {+-} 0.2) eV, both values agree well with recommended values.}
place = {France}
year = {2006}
month = {Nov}
}