Introduction: Monte Carlo method is often applied in radiation therapy as utilized in all the branches of science. An important requirement for successful radiotherapy is carefully examine the dose distribution specifications and decrease the difference between these features with experience to an acceptable level. In this study, the characteristics of 6, 15 and 20 MeV incident x-rays are prov...

Monte Carlo calculations and TLD measurements have been performed for the purpose of characterizing dosimetric properties of new commercially available brachytherapy sources. All sources tested consisted of a solid core, upon which a thin layer of 125I has been adsorbed, encased within a titanium housing. The PharmaSeed BT-125 source manufactured by Syncor is available in silver or palladium co...

Abstract Monte Carlo N-Particle (MCNP) is a widely-used code in nuclear engineering, but it needs high computation times due to the tracking of every single particle and interaction event. This causes shielding optimization using trial-and-error take long complete. It can be solved by multiprocessing, this requires MCNP source which difficult obtain. Therefore, paper aims suggest solution on ho...

background: high-velocity carbon ion beams represent the most advanced tool for radiotherapy of deep-seated tumors. currently, the superiority of carbon ion therapy is more prominent on lung cancer or hepatomas. materials and methods: the data for lateral straggling and projected range of monoenergetic 290 mev/u (3.48 gev) carbon ions in muscle tissue were obtained from the stopping and range o...

Introduction: Nowadays new radiochromic films have an essential role in radiotherapy dosimetry. Properties such as high sensitivity, good reproducibility, high spatial resolution, easy readout and portability have made them attractive for dosimetry, especially in high-dose-gradient regions. Material and Methods: In this study, electron-beam dose distributions in homogenous and heterogeneous pha...

Background: The presence of a wedge filter in the beam trajectory can modify the beam quality and cause some changes in the dosimetry parameters which are usually difficult to be measured directly and accurately. Material and Methods: In this study the MCNP-4C Monte Carlo code was used to simulate the 9 MV photon beam generated by a linear accelerator. Upon getting a good agreement bet...

This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using the Monte Carlo-based MCNPX/MCNPPoliMi code system capable of simulating the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fiss...

Background: Miniature neutron sources with high neutron flux have abundant applications in medicine, industry and researches. The most important general characteristic of miniature neutron sources is their diameter which is 3mm in average. In this research, we have surveyed and designed an Am-Be miniature neutron source fabrication. Materials and Methods: This investigation resulted in creation...

The MCS code is a computer developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation calculation nuclear reactor systems based on Monte Carlo method. currently used to solve two main types physics problems, namely, criticality problems radiation shielding problems. In this paper, capability validated simulating some selected SINBAD (Shielding Integral Benchmark ...