نتایج جستجو برای: mcnp simulation code
تعداد نتایج: 704198 فیلتر نتایج به سال:
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...
One important factor in using an High Purity Germanium (HPGe) detector is its efficiency that highly depends on the geometry and absorption factors, so that when the configuration of source-detector geometry is changed, the detector efficiency must be re-measured. The best way of determining the efficiency of a detector is measuring the efficiency of standard sources. But considering the fact t...
Boron-neutron capture therapy (BNCT) is an experimental radiation treatment modality used for highly malignant tumor treatments. Prior to irradiation with low energetic neutrons, a B compound is located selectively in the tumor cells. The effect of the treatment is based on the high LET radiation released in the B(n,α)Li reaction with thermal neutrons. BNCT has been used experimentally for brai...
---------------------------------------------------------------------***--------------------------------------------------------------------Abstract The dose distribution in irradiation room and the dose rate at each dwell position of 60Co irradiator SVST-Co-60/B have been calculated using MCNP code. The calculated results are useful information to estimate radiation safety and design irradiato...
This paper presents the validation of the Monte Carlo code MCNP-PoliMi for the simulation of nuclear safeguards experiments with plutonium and uranium metal based on fast time-correlation measurements. A comparison is presented between experimental data acquired with the Nuclear Materials Identification System and the Monte Carlo simulations. The measurements and simulations were performed for ...
Nuclear radiation protection and safety is one of the most important principles needed to consider in nuclear labs. At this article, Dr. Shahriari Nuclear Laboratory, was selected as a case study for investigation of total absorbed dose at the different points of the lab to determine the safe or hazardous points in it, according to nuclear radiations safety rules. Therefore, the environment of ...
By use of silicon rubber as polymeric matrix and bismuth oxide as fillers, composite materials were fabricated up to 70 wt% and their gamma ray attenuation was studied. Due to the fair solubility of bismuth oxide particles in polymer matrix, the solution intercalation method is used for nanocomposite fabrication. The applied source for radiation attenuation test was 241Am with photon energies 5...
Accuracy of treatment planning systems may significantly influence the efficacy of brachytherapy. The purpose of this work is a detailed, varied and independent evaluation of an in-house brachytherapy treatment planning software called STPS. Operational accuracy of STPS was investigated. Geometric tests were performed to validate entry and reconstruction of positional information from scanned o...
abstract background: accurate methods of radiation therapy dose calculation. there are different monte carlo codesfor simulation of photons, electrons and the coupled transport of electrons and photons. mcnpis a general purpose monte carlo code that can be used for electron, photon and coupledphoton-electron transport.monte carlo simulation of radiation transport is considered to be one of the ...
Introduction: The CT machine utilizes a bowtie filter to shape the X-ray beam and remove lower energy photons. Configuration of this bowtie filter is complex and its geometry is often not available in detail. It causes the CT dose index (CTDI) be with the different values in measurement versus Monte Carlo simulation studies and other analytical calculations. It is important esp...
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