ABSTRACTBackground: Monte Carlo simulation has been used by many researchers to calculate organ and effective dose of patients arising from conventional X-ray examinations. In this study the radiation transport code, MCNP-4C, has been used to perform Monte Carlo simulations to estimate radiation dose delivered to different organs in conventional X-ray examinations.Material and Methods: In this...

A new algorithm for energy-loss straggling in MCNP is demonstrated. An approximate but accurate energy-loss moment-preserving differential cross section is used in conjunction with single event Monte Carlo simulation through each condensed history step to show that highly accurate energy spectra, leakage currents, and dose profiles can be obtained. This new approach provides a viable and even p...

We introduce a fast and well-structured package for constructing voxel-based computational phantoms as MCNP(X) input file based on CT DICOM images. Our program which has been implemented under a graphic user inter-face provides several basic image processing tools for manipulating images. The MCNP materials are interpreted from the CT numbers of DICOM images. Two modes of phantom creation have ...

Radiotherapy is a common cancer treatment module, where a certain amount of dose will be delivered to the targeted organ. This is achieved usually by photons generated by linear accelerator units. However, radiation scattering within the patient's body and the surrounding environment will lead to dose dispersion to healthy tissues which are not targets of the primary radiation. Determination of...

Mammography is one of the most important imaging techniques to diagnose breast cancer. It is perhaps the single most important innovation in breast cancer control. The importance of mammography is directly related to its value in the early detection and management of breast cancer. Mammography detects approximately 2-3 times as many early breast cancers as physical exams. Breast cancer is the s...

The Monte Carlo method was used to calculate the photon detection efficiency and energy resolution curves for a 1.500 100 NaI(Tl) scintillator detector (crystal þ housing þ photomultiplier tube material equivalent) exposed to gamma rays in the energy range from 20 keV to 662 keV. This work aims to design a precise computational model, based in Monte Carlo simulation, which can be used in practi...

The detailed China Fusion Engineering Test Reactor (CFETR) 22.5° computer aided design (CAD) model is very difficult to convert into Monte Carlo N Particle Transport Code (MCNP). Manually writing MCNP input data complicated, which not only time-consuming but also cannot guarantee accuracy. Therefore, in order improve the efficiency and accuracy of transformation, modeling with CAD using CATIA i...