Calculation of Detection Efficiency for the Gamma Detector using MCNPX

• Authors: İ. Akkurt , H. Tekin , A. Mesbahi
• Languages of publication: EN

Abstracts

EN

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.

Keywords

EN

87.10.Rt; 29.40.-n

Discipline

• 29.40.-n: Radiation detectors(for mass spectrometers, see 07.75.+h; see also 95.55.Vj Neutrino, muon, pion, and other particle detectors; cosmic ray detectors in astronomy)
• 87.10.Rt: Monte Carlo simulations

• Publisher: Institute of Physics, Polish Academy of Sciences
• Journal: Acta Physica Polonica A
• Year: 2015
• Volume: 128
• Issue: 2B
• Pages: B-332-B-334

Dates

published

2015-8

Contributors

author

İ. Akkurt

• Süleyman Demirel University, Faculty of Arts and Science, Physics Department, Isparta, Turkey

author

H. Tekin

• Üsküdar University, Vocational School of Health Services, İstanbul, Turkey,

author

A. Mesbahi

• Dokuz Eylül University, Institute of Health Sciences, Medical Physics Department, İzmir, Turkey

References

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Identifiers

DOI

10.12693/APhysPolA.128.B-332