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Measurements of (n,$\gamma$) neutron capture cross-sections with liquid scintillator detectors

hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorWILSON, J.N.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorHAAS, B.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorBOYER, S.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorDASSIE, D.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorBARREAU, G.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorAICHE, M.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorCZAJKOWSKI, S.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorGROSJEAN, C.
hal.structure.identifierCentre d'Etudes Nucléaires de Bordeaux Gradignan [CENBG]
dc.contributor.authorGUIRAL, A.
dc.date.issued2003
dc.identifier.issn0168-9002
dc.description.abstractEnA method for measuring (n,$\gamma$) neutron capture cross-sections using liquid scintillator detectors has been investigated. If the response function of the detector is known, and the efficiency as a function of energy is low and approximately constant, then gamma cascades can be counted via a method that is independent of the cascade path provided the detector response is manipulated to allow detection efficiency to be proportional to emitted gamma-ray energy. In this paper, we demonstrate the measurement of efficiency and response functions for a C6D6 liquid scintillator using gamma-ray sources and (p,$\gamma$) reactions on light nuclei. Methods to reproduce the detector response and efficiency data successfully using simulations are presented and discussed. An entire response matrix for the detector has been constructed using a new interpolation technique, allowing weighting functions that force the detector efficiency to be proportional to gamma-ray energy to be calculated. An analysis of the sources of error involved in making (n,$\gamma$) cross-section measurements with this method has been undertaken using Monte-Carlo simulation techniques.
dc.language.isoen
dc.publisherElsevier
dc.subject$\gamma$ capture cross sections
dc.subjectLiquid scintillators
dc.subjectResponse functions
dc.subjectWeighting functions
dc.subjectMonte Carlo techniques
dc.titleMeasurements of (n,$\gamma$) neutron capture cross-sections with liquid scintillator detectors
dc.typeArticle de revue
dc.identifier.doi10.1016/S0168-9002(03)01944-2
dc.subject.halPhysique [physics]/Physique Nucléaire Expérimentale [nucl-ex]
bordeaux.journalNuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
bordeaux.page388-399
bordeaux.volume511
bordeaux.peerReviewedoui
hal.identifierin2p3-00103375
hal.version1
hal.popularnon
hal.audienceNon spécifiée
hal.origin.linkhttps://hal.archives-ouvertes.fr//in2p3-00103375v1
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