اندازه‌گیری پرتو گاما در زمینه‌های مختلف تحقیقاتی نیازمند آشکارسازهای کارآمد است. زمینه دزیمتری فوتون آشکارساز جرقه‌ای NaI(Tl) به عنوان یکی از سوسوزن معدنی (غیرآلی)، علت دارا بودن مقدار بالای نور خروجی بسیار حایز اهمیت این پژوهش سعی گردیده است، با کمک کد مونت‌کارلو (MCNPX) مقدمات مشخصه‌یابی توسط و بهره‌گیری روش‌های متفاوت محاسبه دز (تالی‌های 6F، 4*F، 6+F 8*F) انجام شود. طور معمول، یک تابش (شمار...

Abstract Purpose: Advanced radiation therapy techniques use small fields in treatment planning and delivery. Small have the advantage of more accurate dose delivery, but with cost some complications dosimetry. Different calculation algorithms imported various systems (TPSs) which each them has different accuracy. Monte Carlo (MC) simulation been reported as one methods for calculating distribut...

The modelling with the Geant4 toolkit of moderated 3He-filled proportional neutron counters is studied. The energy deposition spectra by the neutron capture products in the gas counter is compared with experimental results. On the other hand, efficiency calculation for polyethylene moderated proportional counters are compared with experimental and MCNPX results.Finally, the application of the G...

objective: different categories are available for estimating of radiation dose. radioisotopes with the same energy and almost the same physical properties have similar effects. monte carlo technique is a computerized method based on mathematical simulation of physical processes. the main purpose of this study is to show that beta particles are not able to penetrate deep into the water. also dif...

In this study, we fabricated a Cerenkov fiber-optic dosimeter (CFOD) without any scintillator to measure Cerenkov radiation signals owing to gamma-rays. The relative depth dose (RDD) distributions of Ir-192 HDR brachytherapy source were obtained by using the CFOD based on a subtraction method and the RDD curve was compared with the simulation result of Monte Carlo N-particle extended transport ...

A novel free release measurement facility (FRMF) was developed within the joint research project "Metrology for Radioactive Waste Management" of the European Metrology Research Programme. Before and during FRMF design and construction, Monte Carlo calculations with MCNPX and PENELOPE codes were used to optimize the thickness of the shielding, the dimensions of the container, and the shape of de...

This paper describes the development of a Graphics Processing Unit (GPU) accelerated Monte Carlo photon transport code, ARCHERGPU, to perform CT imaging dose calculations with good accuracy and performance. The code simulates interactions of photons with heterogeneous materials. It contains a detailed CT scanner model and a family of patient phantoms. Several techniques are used to optimize the...

The need for more accurate radiation therapy treatment planning is driving improvements in radiation transport calculations. In particular, the inclusion of patient specific anatomy and tissue density heterogeneities will be very important, particularly for treatment modalities that involve strong material discontinuities. The study presented here compares the application of the deterministic c...