000205109 001__ 205109
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000205109 037__ $$aFZJ-2015-05579
000205109 041__ $$aEnglish
000205109 1001_ $$0P:(DE-Juel1)130404$$aRossbach, Matthias$$b0$$eCorresponding author
000205109 1112_ $$aModern Trends in Activation Analysis$$cDelft$$d2015-08-24 - 2015-08-28$$gMTAA14$$wThe Netherlands
000205109 245__ $$aFission Neutron PGAA from inelastic scattering reactions – first results of FaNGaS
000205109 260__ $$c2015
000205109 3367_ $$0PUB:(DE-HGF)6$$2PUB:(DE-HGF)$$aConference Presentation$$bconf$$mconf$$s1441885636_16215$$xOther
000205109 3367_ $$033$$2EndNote$$aConference Paper
000205109 3367_ $$2DataCite$$aOther
000205109 3367_ $$2ORCID$$aLECTURE_SPEECH
000205109 3367_ $$2DRIVER$$aconferenceObject
000205109 3367_ $$2BibTeX$$aINPROCEEDINGS
000205109 520__ $$aA beam of fission neutrons extracted at the SR10 beam line of the FRM II Research Reactor in Garching has been used to study inelastic scattering reactions and related product nuclei with a new instrument Fast Neutron Gamma Spectroscopy (FaNGaS). Complimentary to cold neutron PGAA, with FaNGaS (n,n’) reactions induced by fission neutrons can be studied. Prompt Gamma lines from inelastic scattering reactions up to now have been rarely studied and no adequate compilation of the emitted gamma energies exist. In developing non-destructive analytical techniques using neutron generator based PGAA such data are badly needed for quantification of heavy metals and actinides in e.g. nuclear waste, hazardous materials, or safeguards samples.A number of elements and relevant actinides have been irradiated in the fast neutron beam SR10 at the FRM II reactor in Garching, Germany. A heavily shielded 50% eff. HPGe detector perpendicular to the beam is looking at the samples exposed to ≈ 108 cm-2s-1 fission neutrons. Prompt and delayed gamma spectra have been taken and evaluated using the available data in scattered reports. Additional gamma lines have been detected and are being compiled to create a data base for (n,n’) reactions. Particular emphasis is given on actinides including 238U, as well as on shielding materials such as Cd, W and  Pb. Some examples will be given and first results will be discussed in this contribution.
000205109 536__ $$0G:(DE-HGF)POF3-161$$a161 - Nuclear Waste Management (POF3-161)$$cPOF3-161$$fPOF III$$x0
000205109 65027 $$0V:(DE-MLZ)SciArea-220$$2V:(DE-HGF)$$aInstrument and Method Development$$x0
000205109 65017 $$0V:(DE-MLZ)GC-180$$2V:(DE-HGF)$$aOthers$$x0
000205109 693__ $$0EXP:(DE-MLZ)MEDAPP-20140101$$1EXP:(DE-MLZ)FRMII-20140101$$5EXP:(DE-MLZ)MEDAPP-20140101$$6EXP:(DE-MLZ)SR10-20140101$$aForschungs-Neutronenquelle Heinz Maier-Leibnitz $$eMedical Application Facility$$fSR10$$x0
000205109 7001_ $$0P:(DE-Juel1)131296$$aRandriamalala, Tsitohaina$$b1
000205109 7001_ $$0P:(DE-HGF)0$$aRevay, Zsolt$$b2
000205109 7001_ $$0P:(DE-HGF)0$$aSöllradl, S.$$b3
000205109 7001_ $$0P:(DE-HGF)0$$aWagner, F. M.$$b4
000205109 909CO $$ooai:juser.fz-juelich.de:205109$$pVDB
000205109 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130404$$aForschungszentrum Jülich GmbH$$b0$$kFZJ
000205109 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)131296$$aForschungszentrum Jülich GmbH$$b1$$kFZJ
000205109 9131_ $$0G:(DE-HGF)POF3-161$$1G:(DE-HGF)POF3-160$$2G:(DE-HGF)POF3-100$$3G:(DE-HGF)POF3$$4G:(DE-HGF)POF$$aDE-HGF$$bEnergie$$lNukleare Entsorgung und Sicherheit sowie Strahlenforschung$$vNuclear Waste Management$$x0
000205109 9141_ $$y2015
000205109 920__ $$lyes
000205109 9201_ $$0I:(DE-Juel1)IEK-6-20101013$$kIEK-6$$lNukleare Entsorgung und Reaktorsicherheit$$x0
000205109 980__ $$aconf
000205109 980__ $$aVDB
000205109 980__ $$aI:(DE-Juel1)IEK-6-20101013
000205109 980__ $$aUNRESTRICTED
000205109 981__ $$aI:(DE-Juel1)IFN-2-20101013