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Calculation of Detection Efficiency for the Gamma Detector using MCNPX

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dc.creator Mesbahi, A.
dc.creator AKKURT, İskender
dc.creator Tekin, H. O.
dc.date 2015-07-31T21:00:00Z
dc.date.accessioned 2020-10-06T12:03:38Z
dc.date.available 2020-10-06T12:03:38Z
dc.identifier fe145dd0-7546-4843-ac6c-ed8525f315bb
dc.identifier 10.12693/aphyspola.128.b-332
dc.identifier https://avesis.sdu.edu.tr/publication/details/fe145dd0-7546-4843-ac6c-ed8525f315bb/oai
dc.identifier.uri http://acikerisim.sdu.edu.tr/xmlui/handle/123456789/77161
dc.description Radiation detection has been a main interest for researchers as all kind of produced particles in atomic and subatomic physics based on the measurement systems so-called detector. Detection efficiency is one of the main parameter in detection system besides many other different parameters of the detector. The absolute efficiency of the gamma detector system will be used at Turkish Accelerator and Radiation Laboratory at Ankara (TARLA) is simulated using MCNPX code (version 2.4.0). The MCNP is the general purpose MC code that can be used for neutron, photon, electron or coupled neutron, photon, electron transport. The results have been obtained for NaI(Tl) detector system and compared with the experimental results. A good agreement was found between calculation and experiment.
dc.language eng
dc.rights info:eu-repo/semantics/closedAccess
dc.title Calculation of Detection Efficiency for the Gamma Detector using MCNPX
dc.type info:eu-repo/semantics/article


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