نتایج جستجو برای: MCNPX Code

تعداد نتایج: 168222  

2015
M. SAEED E. CHAKIR

This paper presents the Monte Carlo simulation of the Positron Emission Tomography (PET) scanning technique using MCNPX code. The raw data generated by general MCNPX code contain a lot of unnecessary information for the image reconstruction process. This requires a large memory to store all this information. In order to reduce the needed memory, we introduce some modifications on the MCNPX code...

Journal: :Journal of engineering science 2021

Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, exposure involves people during the experiment. On contrary, simulation technique for examining interactions is radio-logically safer, less timeconsuming, cost-effective, applicable all desired sources. Through 48.86 mCi 662 keV Caesium-137 gamma-ray source; ...

Journal: :journal of biomedical physics and engineering 0
m khadem abolfazli babol medical university s r mahdavi iran medical university m mahdavi mazandaran universityسازمان اصلی تایید شده: دانشگاه علوم پزشکی بابل (babol university of medical sciences) gh ataei babol medical universityسازمان اصلی تایید شده: دانشگاه علوم پزشکی ایران (iran university of medical sciences)

background: gold nanoparticles are emerging as promising agents for cancer therapy and are being investigated as drug carriers, photothermal agents, contrast agents and radiosensitisers. objective: the aim of this study is to understand characteristics of secondary electrons generated from interaction of gold nanoparticles gnps with x-rays as a function of nanoparticle size and beam energy and ...

Journal: :Radiation protection dosimetry 2012
Kyle Copeland Wallace Friedberg Tatsuhiko Sato Koji Niita

Secondary radiation in aircraft and spacecraft includes deuterons, tritons and helions. Two sets of fluence-to-effective dose conversion coefficients for isotropic exposure to these particles were compared: one used the particle and heavy ion transport code system (PHITS) radiation transport code coupled with the International Commission on Radiological Protection (ICRP) reference phantoms (PHI...

2011
Zhaopeng Zhong Alberto Talamo Yousry Gohar

The Monte Carlo code MCNPX has been utilized to calculate the effective delayed neutron fraction and reactivity by using the area-ratio method. The effective delayed neutron fraction eff has been calculated with the fission probability method proposed by Meulekamp and van der Marck. MCNPX was used to calculate separately the fission probability of the delayed and the prompt neutrons by using th...

Journal: :iranian journal of medical physics 0
fatemeh razghandi department of physics, school of sciences, ferdowsi university of mashhad, mashhad, iran reza izadi department of physics, school of sciences, ferdowsi university of mashhad, mashhad, iran ali mowlavi department of physics, hakim sabzevari university, sabzevar, iran international centre for theoretical physics, associate and federation schemes, medical physics field, trieste, italy

introduction one of the important applications of nuclear physics in medicine is the use of radioactive elements as radiopharmaceuticals. metastatic bone disease is the most common form of malignant bone tumors. samarium-153-ethylene diamine tetramethylene phosphonate (153sm-edtmp) as a radiopharmaceutical is used for pain palliation. this radiopharmaceutical usually emits beta particles, which...

Journal: :Nuclear Technology and Radiation Protection 2012

2014
Chin-Hui Wu An-Cheng Shiau Yi-Jen Liao Hsin-Yu Lin Yen-Wan Hsueh Liu Shih-Ming Hsu

This study explores how the metal materials of the applicator influence the dose distribution when performing brachytherapy for cervical cancer. A pinpoint ionization chamber, Monte Carlo code MCNPX, and treatment planning system are used to evaluate the dose distribution for a single Ir-192 source positioned in the tandem and ovoid. For dose distribution in water with the presence of the tande...

Journal: :International journal of radiation research 2021

Assessment of secondary particles in breast proton therapy by Monte Carlo simulation code using MCNPX

ژورنال: سنجش و ایمنی پرتو 2020

In this study, cobalt 60 with a mean energy of (1.25 Mev) was used as a photonic source to investigate the effect of decreasing gamma-ray intensity by materials and polymer composite using MCNPX code. First, we investigated the effect of thickness and density on the reduction of gamma ray intensity, and then the comparison between the lead protector, tungsten and polymer composite in several th...

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