نتایج جستجو برای: mcnp monte carlo code

تعداد نتایج: 236688  

Journal: :iranian journal of medical physics 0
lida gholamkar department of medical radiation engineering, science and research branch, islamic azad university, tehran, iran, mahdi sadeghi medical physics department, school of medicine, iran university of medical sciences, tehran, iran ali asghar mowlavi physics department, school of sciences, hakim sabzevari university, sabzevar, iran. ictp, associate federation scheme, medical physics field, trieste, italy. mitra athari department of medical radiation engineering, science and research branch, islamic azad university, tehran, iran,

introduction one of the best methods in the diagnosis and control of breast cancer is mammography. the importance of mammography is directly related to its value in the detection of breast cancer in the early stages, which leads to a more effective treatment. the purpose of this article was to calculate the x-ray spectrum in a mammography system with monte carlo codes, including mcnpx and mcnp5...

2006
RICHARD H. OLSHER

With the advent of inexpensive computing power over the past two decades, applications of Monte Carlo radiation transport techniques have proliferated dramatically. At Los Alamos, the Monte Carlo codes MCNP5 [1] and MCNPX [2] are used routinely on personal computer platforms for radiation shielding analysis and dosimetry calculations. These codes are attractive for such applications because of ...

2003
Patrick N. McDermott Tongming He A. DeYoung

The dose calculation accuracy of a commercial pencil beam IMRT planning system is evaluated by comparison with Monte Carlo calculations and measurements in an anthropomorphic phantom. The target volume is in the right lung and mediastinum and thus significant tissue inhomogeneities are present. The Monte Carlo code is an adaptation of the MCNP code and the measurements were made with TLD and fi...

A.A. Mowlavi, M. Yazdani,

Background: Monte Carlo determination of TG-43 brachytherapy dosimetry parameters and dose distribution calculation for 131Cs source model CS-1 are presented in this study. Materials and Methods: The dose distribution was calculated around the 131Cs Model CS-1 located in the center of 30 cm ×30 cm ×30 cm water, and soft tissue phantoms cube using MCNP code by Monte Carlo method. The percentage ...

2007
PW Chin JP Giddy DG Lewis DW Walker

We present a computing framework for Monte Carlo simulation of radiation transport. In conformity with our belief that Monte Carlo studies should be anchored to physics but not to any particular code, we have enabled different Monte Carlo codes in this environment. The framework embraces the EGSnrc family, FLUKA, MCNP/MCNPX, GEANT4 and PENELOPE; dedicated and non-dedicated resources; shared and...

Journal: :iranian journal of radiation research 0
a. mostaar medical physics department, tehran university of medical sciences, tehran, iran m. allahverdi department of radiotherapy physics, cancer institute, tehran, iran m. shahriari gamma irradiation center, atomic energy organization of iran, tehran, iran

background: in treating patients with radiation, the degree of accuracy for the delivery of tumor dose is recommended to be within ± 5% by icru in report 24. the experimental studies have shown that the presence of low-density inhomogeneity in areas such as the lung can lead to a greater than 30% change in the water dose data. therefore, inhomogeneity corrections should be used in treatment pla...

ژورنال: کومش 2019
Jadidi , Majid , Rajabi , Hossein , Tajik-mansoury , Mohammad Ali, Taleshi Ahangari , Hadi ,

Introduction: Now day Ionizing radiation has found increasing applications in cancer treatment. However, in the treatment different kinds and size of tumors especially metastatic and small size tumors, conventional methods of external radiation therapy are not common. In radionuclide therapy, the use of monoclonal antibodies has made it possible to achieve maximum dose to small size tumor and m...

2005
R. Jeraj

MCNP is widely used Monte Carlo program in reactor and nuclear physics. However, an option of simulating electrons was added into the code a few years ago. With this extension MCNP became a code, potentially applicable for applications in medical physics. In 1997, a new version of the code, named MCNP4B was released, which contains several improvements in electron transport modelling. To test s...

پایان نامه :وزارت علوم، تحقیقات و فناوری - دانشگاه صنعتی اصفهان - دانشکده فیزیک 1388

ضرایب انباشت داده های مهمی در مسئله ی حفاظ سازی در مقابل تابش های هسته ای از جمله تابش گاما هستند که پاسخ آشکارساز به فوتون های بدون برخورد را تصحیح می کنند. دانستن ضریب انباشت برای مواد مختلف و ترکیبات آن ها از اهمیت زیادی برخوردار است. در این پایان نامه ابتدا ضریب انباشت پرتودهی تابش گاما برای حفاظ کروی دو لایه ای ساخته شده از آب و سرب که ضخامت کل حفاظ بین mfp2 تا mfp10 تغییر می کرد با استفاد...

2015
Amaal A. Tawfik Moustafa Aziz

The dose distribution inside the Gamma Cobalt irradiation therapy unit at Egyptian Atomic Energy Authority (EAEA) was determined both experimentally and theoretically. MCNP computer code, based on Monte Carlo method, was used to model the unit and calculate the dose distributions in both normal and emergency situation of the unit. The dose distribution inside the unit was also measured during t...

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