Background: Monte Carlo (MC) modeling of a linear accelerator is a prerequisite for Monte Carlo dose calculations in external beam radiotherapy. In this study, a simple and efficient model was developed for Elekta SL-25 linear accelerator using MCNP4C Monte Carlo code Materials and methods: The head of Elekta SL-25 linac was simulated for 6 and 18 MV photon beams using MCNP4C MC code. Energ...

Underwater vehicle is designed to ensure the security of country sea boundary, providing harsh requirements for its power system design. Conventional power sources, such as battery and Stirling engine, are featured with low power and short lifetime. Micronuclear reactor power source featured with higher power density and longer lifetime would strongly meet the demands of unmanned underwater veh...

background: recently, different investigators have studied the possibility of radiation therapy in restenosis prevention and have shown promising results. in this study a unique radioactive source for intra vascular brachytherapy (ivbt) was investigated. the two-dimensional dose distribution in water for a 32p ivbt stent has been calculated. the pure beta emitter source 32p has been coated on p...

In this paper, we present a neutron spectrum unfolding technique based on a modification of the least-squares method. The main innovation is the use of a Krylov subspace iteration method to solve the least-squares normal equations. This method was employed because it performs better on ill-conditioned systems of linear equations as compared with standard direct-solution methods. Three different...

A Monte Carlo shielding model for PET/CT clinics Robert L. Metzger and Kenneth A. Van Riper Radiation Safety Engineering, Inc Chandler, AZ Abstract Modern PET/CT clinics consist of a scanner room housing the double gantry PET/CT unit and a control area, two or more quiet rooms where patients rest prior to scanning, and a hot lab where doses are prepared. Of these areas, the scanner room, quiet ...

The true coincidence effect is studied in two High Purity Germanium (HPGe) detectors for a variety of isotopes, source geometries and to detector configurations, via computational tools based on Monte–Carlo simulations. Τhe upgraded patch MCNP code MCNP–CP the 2018 version PENELOPE, which take into account decay scheme each cascade emitter, are used calculate Full Energy Peak Efficiency (FEPE) ...

background: monte carlo (mc) modeling of a linear accelerator is a prerequisite for monte carlo dose calculations in external beam radiotherapy. in this study, a simple and efficient model was developed for elekta sl-25 linear accelerator using mcnp4c monte carlo code materials and methods: the head of elekta sl-25 linac was simulated for 6 and 18 mv photon beams using mcnp4c mc code. energy sp...

PURPOSE Radiopharmaceutical applications in nuclear medicine require a detailed dosimetry estimate of the radiation energy delivered to the human tissues. Over the past years, several publications addressed the problem of internal dose estimate in volumes of several sizes considering photon and electron sources. Most of them used Monte Carlo radiation transport codes. Despite the widespread use...

objective: the passage of ionizing radiation in living cells creates clusters of damaged nucleotides in dna. in this study, dna strand breaks induced by the beta particle of iodine-131 (i-131), have been determined experimentally and compared to monte carlo simulation results as a theoretical method of determining131i damage. materials and methods: in this experimental study, in order to create...

The MCNP code is a general Monte Carlo N-Particle Transport program that is widely used in health physics, medical physics and nuclear engineering for problems involving neutron, photon and electron transport. However, due to the stochastic nature of the algorithms employed to solve the Boltzmann transport equation, MCNP generally exhibits a slow rate of convergence. In fact, engineers and scie...