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        Capabilities of the Monte Carlo Simulation Codes for Modeling of a Small Animal SPECT Camera

        Alireza Sadremomtaz,Zeinab Telikani 대한핵의학회 2018 핵의학 분자영상 Vol.52 No.4

        Purpose This study aims to compare Monte Carlo-based codes’ characteristics in the determination of the basic parameters of ahigh-resolution single photon emission computed tomography (HiReSPECT) scanner. Methods The geometry of this dual-head gamma camera equipped with a pixelated CsI(Na) scintillator and lead hexagonal holecollimator were accurately described in the GEANT4 Application for the Tomographic Emission (GATE), Monte Carlo N-particleextended (MCNP-X), and simulation of imaging nuclear detectors (SIMIND) codes.We implemented simulation procedures similarto the experimental test for calculation of the energy spectra, spatial resolution, and sensitivity of HiReSPECT by using 99mTc sources. Results The energy resolutions simulated by SIMIND, MCNP-X, and GATE were 17.53, 19.24, and 18.26%, respectively, whileit was calculated at 19.15% in experimental test. The average spatial resolutions of the HiReSPECT camera at 2.5 cm from thecollimator surface simulated by SIMIND, MCNP-X, and GATE were 3.18, 2.9, and 2.62 mm, respectively, while this parameterwas reported at 2.82 mm in the experiment test. The sensitivities simulated by SIMIND, MCNP-X, and GATE were 1.44, 1.27,and 1.38 cps/μCi, respectively, on the collimator surface. Conclusions Comparison between simulation and experimental results showed that among these MC codes, GATE enabled toaccurately model realistic SPECT system and electromagnetic physical processes, but it required more time and hardwarefacilities to run simulations. SIMIND was the most flexible and user-friendly code to simulate a SPECT camera, but it hadlimitations in defining the non-conventional imaging device. The most important characteristics like time and speed of simulation,preciseness of results, and user-friendliness should be considered during simulations.

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        Investigation of Dose Distribution in Mixed Neutron-Gamma Field of Boron Neutron Capture Therapy using N-Isopropylacrylamide Gel

        Elham Bavarnegin,Hossein Khalafi,Alireza Sadremomtaz,Yaser Kasesaz,Azim Khajeali 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.1

        Gel dosimeters have unique advantages in comparison with other dosimeters. Until now, these gels have been used in different radiotherapy techniques as a reliable dosimetric tool. Because dose distribution measurement is an important factor for appropriate treatment planning in different radiotherapy techniques, in this study, we evaluated the ability of the N-isopropylacrylamide (NIPAM) polymer gel to record the dose distribution resulting from the mixed neutron-gamma field of boron neutron capture therapy (BNCT). In this regard, a head phantom containing NIPAM gel was irradiated using the Tehran Research Reactor BNCT beam line, and then by a magnetic resonance scanner. Eventually, the R2 maps were obtained in different slices of the phantom by analyzing T2-weighted images. The results show that NIPAM gel has a suitable potential for recording threedimensional dose distribution in mixed neutron-gamma field dosimetry.

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