000172930 001__ 172930
000172930 005__ 20240712084605.0
000172930 037__ $$aFZJ-2014-06360
000172930 1001_ $$0P:(DE-Juel1)156285$$aSchumann, Manuel$$b0$$eCorresponding Author$$ufzj
000172930 1112_ $$a25th Seminar on Activation Analysis and Gamma Spectroscopy$$cAachen$$d2015-02-23 - 2015-02-25$$gSAAGAS$$wDeutschland
000172930 245__ $$aFast Neutron Imaging with an aSi Detector for Nuclear Waste Assay
000172930 260__ $$c2015
000172930 3367_ $$0PUB:(DE-HGF)1$$2PUB:(DE-HGF)$$aAbstract$$babstract$$mabstract$$s1417445716_27072
000172930 3367_ $$033$$2EndNote$$aConference Paper
000172930 3367_ $$2DataCite$$aOutput Types/Conference Abstract
000172930 3367_ $$2ORCID$$aOTHER
000172930 3367_ $$2DRIVER$$aconferenceObject
000172930 3367_ $$2BibTeX$$aINPROCEEDINGS
000172930 520__ $$aIntroduction: Radioactive waste has to undergo a process of quality checking in order to check its conformance with national regulations prior to its transport, intermediate storage and final disposal. Within the quality checking of radioactive waste packages non-destructive assays are required to characterize their radiotoxic and chemotoxic contents. In a cooperation framework Forschungszentrum Jülich GmbH, RWTH Aachen University and Siemens AG are studying the feasibility of a compact Neutron Imaging System for Radioactive waste Analysis (NISRA) using 14 MeV neutrons. Fast neutron imaging is a promising technique to assay large and dense items providing in complementarity to photon imaging additional information on the presence of structures in radioactive waste packages. However due to the low neutron emission of neutron generators the challenging task resides in the development of an imaging detector with a high efficiency, a low sensitivity to gamma radiation and a resolution sufficient for the purpose.Setup: The setup of the experiment is shown in Figure 1. The 14 MeV neutrons are produced by a D-T neutron generator. Neutron detection is achieved using a 40 x 40 cm² amorphous silicon (aSi) flat panel detector linked to a plastic scintillator. The detector thermal noise was reduced by employing an entrance windows made of aluminium. The optimal gain and integration time were obtained by measuring the response of the detector to the radiation of a 241Am source.Performance Tests: First test measurements were carried out with different materials made of Al, C, Fe, Pb, W, concrete and polyethylene (50 x 80 x 100 mm³). Each sample was irradiated with PE as a reference. Data analysis was performed with a homemade algorithm which allows determining a value related to the neutron absorption.Results: First neutron radiographies were successfully recorded despite the low detector efficiency and low neutron intensity. In addition the correlation between the absorption and measured signal attenuation was determined and is shown in figure 2. The measurements and results will be presented and discussed.
000172930 536__ $$0G:(DE-HGF)POF3-161$$a161 - Nuclear Waste Management (POF3-161)$$cPOF3-161$$fPOF III$$x0
000172930 536__ $$0G:(DE-Juel1)HITEC-20170406$$aHITEC - Helmholtz Interdisciplinary Doctoral Training in Energy and Climate Research (HITEC) (HITEC-20170406)$$cHITEC-20170406$$x1
000172930 7001_ $$0P:(DE-Juel1)133882$$aEngels, Ralf$$b1$$ufzj
000172930 7001_ $$0P:(DE-HGF)0$$aFrank, Martin$$b2
000172930 7001_ $$0P:(DE-Juel1)156470$$aFurletova, Julia$$b3$$ufzj
000172930 7001_ $$0P:(DE-Juel1)156247$$aFurletov, Sergey$$b4
000172930 7001_ $$0P:(DE-Juel1)130352$$aHavenith, Andreas$$b5$$ufzj
000172930 7001_ $$0P:(DE-Juel1)133902$$aKemmerling, Günter$$b6$$ufzj
000172930 7001_ $$0P:(DE-Juel1)130362$$aKettler, John$$b7$$ufzj
000172930 7001_ $$0P:(DE-HGF)0$$aKlapdor-Kleingrothaus, Thorwald$$b8
000172930 7001_ $$0P:(DE-Juel1)130382$$aMauerhofer, Eric$$b9$$ufzj
000172930 7001_ $$0P:(DE-Juel1)8460$$aSchitthelm, Oliver$$b10$$ufzj
000172930 7001_ $$0P:(DE-HGF)0$$aVasques, Richard$$b11
000172930 7001_ $$0P:(DE-HGF)0$$aVoß, Dirk$$b12
000172930 773__ $$y2015
000172930 8564_ $$uhttps://juser.fz-juelich.de/record/172930/files/FZJ-2014-06360.pdf$$yRestricted
000172930 909CO $$ooai:juser.fz-juelich.de:172930$$pVDB
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)156285$$aForschungszentrum Jülich GmbH$$b0$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)133882$$aForschungszentrum Jülich GmbH$$b1$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)156470$$aForschungszentrum Jülich GmbH$$b3$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130352$$aForschungszentrum Jülich GmbH$$b5$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)133902$$aForschungszentrum Jülich GmbH$$b6$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130362$$aForschungszentrum Jülich GmbH$$b7$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)130382$$aForschungszentrum Jülich GmbH$$b9$$kFZJ
000172930 9101_ $$0I:(DE-588b)5008462-8$$6P:(DE-Juel1)8460$$aForschungszentrum Jülich GmbH$$b10$$kFZJ
000172930 9141_ $$y2015
000172930 9130_ $$0G:(DE-HGF)POF2-142$$1G:(DE-HGF)POF2-140$$2G:(DE-HGF)POF2-100$$aDE-HGF$$bEnergie$$lNukleare Sicherheitsforschung$$vSafety Research for Nuclear Waste Disposal$$x0
000172930 9131_ $$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$$x0
000172930 920__ $$lno
000172930 9201_ $$0I:(DE-Juel1)IEK-6-20101013$$kIEK-6$$lNukleare Entsorgung und Reaktorsicherheit$$x0
000172930 980__ $$aabstract
000172930 980__ $$aVDB
000172930 980__ $$aI:(DE-Juel1)IEK-6-20101013
000172930 980__ $$aUNRESTRICTED
000172930 981__ $$aI:(DE-Juel1)IFN-2-20101013