Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources
The present work concerns the development of a technique for activity determination of 68Ge/68Ga and 57Co disused radioactive sources. This technique aims to determine the activity of these sources by measuring and Monte Carlo simulation using the MCNPX code. Therefore, efficiency calib...
| Main Authors: | , , , , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
VINCA Institute of Nuclear Sciences
2023-01-01
|
| Series: | Nuclear Technology and Radiation Protection |
| Subjects: | |
| Online Access: | https://doiserbia.nb.rs/img/doi/1451-3994/2023/1451-39942301053M.pdf |
| _version_ | 1797748902661718016 |
|---|---|
| author | Mavrikis Dimitris Siarafera Tatiana Ntalla Eleni Markopoulos Angelos Ioannidou Alexandra Savidou Anastasia |
| author_facet | Mavrikis Dimitris Siarafera Tatiana Ntalla Eleni Markopoulos Angelos Ioannidou Alexandra Savidou Anastasia |
| author_sort | Mavrikis Dimitris |
| collection | DOAJ |
| description | The present work concerns the development of a technique for
activity determination of 68Ge/68Ga and 57Co disused radioactive sources.
This technique aims to determine the activity of these sources by measuring
and Monte Carlo simulation using the MCNPX code. Therefore, efficiency
calibrations of the 3 x 3 NaI(Tl) detector for specific source geometries
were carried out. Spectrums for two types of disused radioactive sources
were collected for different measurement times. The characteristic gamma
rays of a flood source containing 57Co and a line source containing
68Ge/68Ga, were used. In case of 68Ge/68Ga, the annihilation peak of 511
keV was also used considering the disused radioactive sources as a
positron emitter. Sources of the mentioned types with certified
nominal activities were used to validate MCNPX models. For the 57Co
source, 15 minutes measuring time was adequate for activity determination,
and 2 hours measuring time provided adequate sensitivity, at the level of
general clearance. For 68Ge/68Ga line source, 15 minutes measurement was
adequate for activity determination by using the 511 keV from the
annihilation of 1899.1 keV positrons. |
| first_indexed | 2024-03-12T16:12:38Z |
| format | Article |
| id | doaj.art-8ef00d602f524163809f97db9890d0ff |
| institution | Directory Open Access Journal |
| issn | 1451-3994 1452-8185 |
| language | English |
| last_indexed | 2024-03-12T16:12:38Z |
| publishDate | 2023-01-01 |
| publisher | VINCA Institute of Nuclear Sciences |
| record_format | Article |
| series | Nuclear Technology and Radiation Protection |
| spelling | doaj.art-8ef00d602f524163809f97db9890d0ff2023-08-09T12:42:29ZengVINCA Institute of Nuclear SciencesNuclear Technology and Radiation Protection1451-39941452-81852023-01-01381535810.2298/NTRP2301053M1451-39942301053MMeasurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sourcesMavrikis Dimitris0Siarafera Tatiana1Ntalla Eleni2Markopoulos Angelos3Ioannidou Alexandra4Savidou Anastasia5Nuclear Physics Laboratory, School of Physics, Aristotle University of Thessaloniki, Thessaloniki, Greece + National Centre for Scientific Research “Demokritos”, Agia Paraskevi, GreeceNuclear Physics Laboratory, School of Physics, Aristotle University of Thessaloniki, Thessaloniki, GreeceNational Centre for Scientific Research “Demokritos”, Agia Paraskevi, GreeceNational Centre for Scientific Research “Demokritos”, Agia Paraskevi, GreeceNuclear Physics Laboratory, School of Physics, Aristotle University of Thessaloniki, Thessaloniki, GreeceNational Centre for Scientific Research “Demokritos”, Agia Paraskevi, GreeceThe present work concerns the development of a technique for activity determination of 68Ge/68Ga and 57Co disused radioactive sources. This technique aims to determine the activity of these sources by measuring and Monte Carlo simulation using the MCNPX code. Therefore, efficiency calibrations of the 3 x 3 NaI(Tl) detector for specific source geometries were carried out. Spectrums for two types of disused radioactive sources were collected for different measurement times. The characteristic gamma rays of a flood source containing 57Co and a line source containing 68Ge/68Ga, were used. In case of 68Ge/68Ga, the annihilation peak of 511 keV was also used considering the disused radioactive sources as a positron emitter. Sources of the mentioned types with certified nominal activities were used to validate MCNPX models. For the 57Co source, 15 minutes measuring time was adequate for activity determination, and 2 hours measuring time provided adequate sensitivity, at the level of general clearance. For 68Ge/68Ga line source, 15 minutes measurement was adequate for activity determination by using the 511 keV from the annihilation of 1899.1 keV positrons.https://doiserbia.nb.rs/img/doi/1451-3994/2023/1451-39942301053M.pdfgamma-ray spectrometrymcnpxclearancesealed radioactive source characterization |
| spellingShingle | Mavrikis Dimitris Siarafera Tatiana Ntalla Eleni Markopoulos Angelos Ioannidou Alexandra Savidou Anastasia Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources Nuclear Technology and Radiation Protection gamma-ray spectrometry mcnpx clearance sealed radioactive source characterization |
| title | Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources |
| title_full | Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources |
| title_fullStr | Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources |
| title_full_unstemmed | Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources |
| title_short | Measurement technique for characterization and recording of spent 57Co and 68Ge/68Ga sealed radioactive sources |
| title_sort | measurement technique for characterization and recording of spent 57co and 68ge 68ga sealed radioactive sources |
| topic | gamma-ray spectrometry mcnpx clearance sealed radioactive source characterization |
| url | https://doiserbia.nb.rs/img/doi/1451-3994/2023/1451-39942301053M.pdf |
| work_keys_str_mv | AT mavrikisdimitris measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources AT siaraferatatiana measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources AT ntallaeleni measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources AT markopoulosangelos measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources AT ioannidoualexandra measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources AT savidouanastasia measurementtechniqueforcharacterizationandrecordingofspent57coand68ge68gasealedradioactivesources |