زد فایل

مرجع دانلود فایل ,تحقیق , پروژه , پایان نامه , فایل فلش گوشی

زد فایل

مرجع دانلود فایل ,تحقیق , پروژه , پایان نامه , فایل فلش گوشی

Photoneutron production and backscattering in high density concretes used for radiation therapy shielding

اختصاصی از زد فایل Photoneutron production and backscattering in high density concretes used for radiation therapy shielding دانلود با لینک مستقیم و پر سرعت .

In the current study, the effect of high density concretes on photoneutron productions in radiation therapy was studied using Monte Carlo simulations. The photon and neutron spectra of an 18 MeV photon beam of the Varian linac head were used for all simulations. Ordinary and five high density concretes made of high density elements were simulated. The studied concretes consisted of Magnetite, Datolite-Galena, Magnetite–Steel, Limonite–Steel, and Serpentine. Our results showed that photoneutron production in these concretes strongly depends on their composition. It appears that the application of high density elements with higher probability for photoneutron production, such as Fe and Pb, increases the photoneutron production in concrete walls of radiation therapy bunkers. Further studies on the effect of concrete composition on photoneutrons in radiation therapy room are recommended.


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Photoneutron production and backscattering in high density concretes used for radiation therapy shielding

SOFTWARE FOR MEDICAL IMAGE BASED PHANTOM MODELING

اختصاصی از زد فایل SOFTWARE FOR MEDICAL IMAGE BASED PHANTOM MODELING دانلود با لینک مستقیم و پر سرعت .

Latest treatment planning systems depends strongly on CT images, so the tendency is that the
dosimetry procedures in nuclear medicine therapy be also based on images, such as magnetic
resonance imaging (MRI) or computed tomography (CT), to extract anatomical and histological
information, as well as, functional imaging or activities map as PET or SPECT. This information
associated with the simulation of radiation transport software is used to estimate internal dose in
patients undergoing treatment in nuclear medicine.

This work aims to re-engineer the software SCMS, which is an interface software between the
Monte Carlo code MCNP, and the medical images, that carry information from the patient in
treatment. In other words, the necessary information contained in the images are interpreted and
presented in a specific format to the Monte Carlo MCNP code to perform the simulation of
radiation transport. Therefore, the user does not need to understand complex process of inputting
data on MCNP, as the SCMS is responsible for automatically constructing anatomical data from
the patient, as well as the radioactive source data. The SCMS was originally developed in Fortran-
77. In this work it was rewritten in an object-oriented language (JAVA). New features and data
options have also been incorporated into the software. Thus, the new software has a number of
improvements, such as intuitive GUI and a menu for the selection of the energy spectra
correspondent to a specific radioisotope stored in a XML data bank. The new version also supports
new materials and the user can specify an image region of interest for the calculation of absorbed
dose.


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SOFTWARE FOR MEDICAL IMAGE BASED PHANTOM MODELING

استاندارد API 6FA در خصوص تست آتش شیرها (Fire Test for Valves) نسخه 2011

اختصاصی از زد فایل استاندارد API 6FA در خصوص تست آتش شیرها (Fire Test for Valves) نسخه 2011 دانلود با لینک مستقیم و پر سرعت .

استاندارد API 6FA در خصوص تست آتش شیرها (Fire Test for Valves) نسخه 2011


استاندارد API 6FA در خصوص تست آتش شیرها (Fire Test for Valves) نسخه 2011

 

 

 

شما می توانید استاندارد های مورد نیاز خود را  از طریق elmifile@gmail.com به ما اعلام کنید

تا در اسرع وقت در فروشگاه ثبت و به شما اطلاع رسانی گردد... 

 

 

 

 

استاندارد API 6FA

تست آتش شیرها (Fire Test for Valves)

نسخه 2011

 

جهت مشاهده فهرست و کیفیت فایل این استاندارد اینجا را کلیک کنید


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استاندارد API 6FA در خصوص تست آتش شیرها (Fire Test for Valves) نسخه 2011

ENDF66b For MCNPX 5

اختصاصی از زد فایل ENDF66b For MCNPX 5 دانلود با لینک مستقیم و پر سرعت .

کتابخانه Endf66b مختص نسخه mcnpx 5 

حجم این کتابخانه 175.3 مگابایت میباشد و پس از دانلود فایل حاوی لینک دانلود فایل میتوانید براحتی و با اسودگی اقدام به دانود نمایید از انجا که این ادرس لینک مختص فرد میباشد لذا فرد میتواند در صورت بروز مشکل یا قطعی در شبکه مجددا اقدام به دانلود نماید

گروه پژوهشی افق امید نو

علی اصغر محمدزاده

physics.scholars@gmail.com


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ENDF66b For MCNPX 5