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Calculation of Detection Efficiency for the Gamma Detector using MCNPX

100%
Akkurt İ., Tekin H., Mesbahi A.
Acta Physica Polonica A
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2015
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vol. 128
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issue 2B
B-332-B-334
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.
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Photoneutron Dose Measurement in Radiotherapy Room

100%
Kara Ü., Mesbahi A., Akkurt I.
Acta Physica Polonica A
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2015
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vol. 128
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issue 2B
B-372-B-374
EN
Cancer is one of the main disease to threat for human health. Besides surgery and medical treatment (chemotherapy), radiotherapy is commonly used treatment method to kill cancer cell. For this method high energy photon is required. Clinic Lineer Accelerator (cLINAC) relatively lower energy than other LINAC has been used to obtain photon via bremsstrahlung processes. When accelerated electron beam impinges to the thin target bremsstrahlung occurs and photon can be created. Those photons can be focused on cancer cell and kill cancer. In order to focus photon beam collimator materials in LINAC head generally contains heavy elements is used and the interaction of bremsstrahlung photon with the such heavy nuclei the neutron can be produced inside the treatment rooms. The threshold of the neutron production for those materals is about 10 MeV. As the neutron is more dangerous than photon it is important to determine neutron dose during radiotherapy treatment. In this study neutron dose rate has been measured and simulated in radiotherapy room.
3
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Monte Carlo Simulation of Photoneutron Dose in Radiotherapy Room as A Function of Gantry Angles

100%
Kara Ü., Mesbahi A., Akkurt I.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-378-B-380
EN
Using bremsstrahlung photon is one of the principal means to treat cancer. Bremsstrahlung photons are created in medical LINAC and the interaction of bremsstrahlung photon with the heavy nuclei that constitute the linac head shielding is the main process of neutron production inside the treatment rooms. The threshold of the neutron production for those materals is about 10 MeV. As the neutron is more dangerous than photon it is important to determine neutron dose during radiotherapy treatment. The neutron distribution depends on some parameters such as gantry angle. In this study neutron dose rate has been simulated as a function of gantry angle.
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