نتایج جستجو برای: mcnp simulation code

تعداد نتایج: 704198  

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...

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...

Journal: :Health physics 2017
Michael W McNaughton Jessica M Gillis Elizabeth Ruedig Jeffrey J Whicker David P Fuehne

Standard plume models can underestimate the gamma-ray dose when most of the radioactive material is above the heads of the receptors. Typically, a model is used to calculate the air concentration at the height of the receptor, and the dose is calculated by multiplying the air concentration by a concentration-to-dose conversion factor. Models indicate that if the plume is emitted from a stack du...

Journal: :iranian journal of radiation research 0
kakavand 1 department of physics, zanjan university, zanjan, iran ghafourian atomic energy organization of iran, tehran, iran haji-shafeieha 1 department of physics, zanjan university, zanjan, iran

background: miniature neutron sources with high neutron flux have abundant applications in medicine, industry and researches. the most important general characteristic of miniature neutron sources is their diameter which is 3mm in average. in this research, we have surveyed and designed an am-be miniature neutron source fabrication. materials and methods: this investigation resulted in creation...

Journal: :Physics in medicine and biology 2002
John J Demarco Robert E Wallace Kirsten Boedeker

Monte Carlo calculations are frequently used to analyse a variety of radiological science applications using low-energy (10-1000 keV) photon sources. This study seeks to create a low-energy benchmark for the MCNP Monte Carlo code by simulating the absolute dose rate in water and the air-kerma rate for monoenergetic point sources with energies between 10 keV and 1 MeV. The analysis compares four...

ژورنال: سنجش و ایمنی پرتو 2020

In this study, the neutron and gamma doses in the dry channel and in the internal irradiation site of the Miniature Neutron Source research reactor (MNSR) has been calculated and measured. The MNSR reactor is a light water reactor with a maximum power of 30 kW and equipped with various irradiation facilities, including five irradiated sites, five irradiation sites and a dry channel. The interna...

2007
Hashem Miri Hakimabad Hamed Panjeh

Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard γ-ray sources to check their accuracy. γ-rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector struct...

2007
Hashem Miri Hakimabad Hamed Panjeh Alireza Vejdani-Noghreiyan

Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard -ray sources to check their accuracy. -rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector structur...

Journal: :Nuclear Technology and Radiation Protection 2013

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