Results 41 to 50 of about 5,690 (213)

Monte Carlo analysis of energy deposition and X-ray fluence in cylindrical anode systems. [PDF]

open access: yesJ Appl Clin Med Phys
Abstract Background Cylindrical anode X‐ray systems are increasingly used in multisource imaging; however, electron beam interactions with the curved anodes cause geometric distortions that alter energy deposition and X‐ray emission. Understanding these effects is key to optimizing system performance.
Alharbi MKM   +4 more
europepmc   +2 more sources

Monitoring internal contamination from OEW of an 18F-FDG production plant: WBC or head counting setup?

open access: yesBrazilian Journal of Radiation Sciences, 2019
The production 18F-FDG for positron emission tomography (PET) has consistently increased over the past two decades. The risk of internal contamination at 18F-FDG production facilities exists.
Bruno Melo Mendes   +3 more
doaj   +1 more source

The investigation of gamma-ray and neutron shielding parameters of Na2O-CaO-P2O5-SiO2 bioactive glasses using MCNPX code

open access: yesResults in Physics, 2019
Bioactive glasses are silicate glasses with sodium, calcium and phosphorus in its composition used to fulfill or support the functions of living tissues in the human body.
H. O. Tekin   +6 more
semanticscholar   +1 more source

Estudo do fluxo neutrônico no reator IPR-R1 com o MCNPX

open access: yesBrazilian Journal of Radiation Sciences, 2016
Neste trabalho utilizou-se o código computacional MCNPX, uma das versões mais recentes do código de transporte MCNP, com o objetivo de estudar a distribuição do fluxo e sua fluência neutrônica em função da energia em dois dispositivos de irradiação do ...
Júlio Ângelo de Souza Melo   +2 more
doaj   +1 more source

An investigation on shielding properties of BaO, MoO3 and P2O5 based glasses using MCNPX code

open access: yesResults in Physics, 2019
In the present work, some radiation shielding quantities (mass attenuation coefficients, effective atomic number, effective electron density, half value layer and mean free path) for various BaO–MoO3–P2O5 ternary glass systems have been determined within
O. Agar   +5 more
semanticscholar   +1 more source

MCNPX Simulation for Radiation Dose Absorption of Anatomical Regions and Some Organs

open access: yes, 2020
MCNPX Simulation for Radiation Dose Absorption of Anatomical Regions and Some Organs E.E. Altunsoya,b,c,∗, H.O. Tekin, A. Mesbahi and I. Akkurt Üsküdar University, Vocational School of Health Services, Medical Imaging Department, Istanbul 34662, Turkey ...
E. Altunsoy   +3 more
semanticscholar   +1 more source

مقاله پژوهشی: تعیین بیشترین میزان فعالیت مجاز چشمۀ میله‌ای کبالت‌ـ60 برای وجه‌های کاربردی مختلف در داخل اتاقک سربی [PDF]

open access: yesفیزیک کاربردی ایران, 2020
محصورسازی چشمه‌های تابش یکی از مهمترین روش‌های کنترل خطرات بهداشت محیط برای جلوگیری از آسیب‌‌‌رسانی به انسآن‌هاست. معمولاً از اتاقک سربی با دیوارهایی از آجر سربی برای محصورسازی چشمه‌های دارای خطر پرتوزایی متوسط و کم استفاده می‌شود.
رضا باقری   +1 more
doaj   +1 more source

Assessment of the usability conditions of Sb2O3–PbO–B2O3 glasses for shielding purposes in some medical radioisotope and a wide gamma-ray energy spectrum

open access: yesApplied Rheology, 2022
We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb2O3·(40 − x)PbO·60B2O3·0.5CuO and (where; 0 ≤ x ≤ 40 mol%). Phy-X/PSD and MCNPX (version 2.
ALMisned Ghada   +6 more
doaj   +1 more source

A comparative Monte Carlo simulation study on shielding features of the CaF2–CaO–B2O3–P2O5–SrO–Ta2O5 glass system against X-ray by GEANT4 and MCNPX codes

open access: yesScientific Reports
Regarding to their unique physical and mechanical features, glasses and glass–ceramics are suitable materials for shielding purposes. The present study evaluates the shielding properties of the CaF2–CaO–B2O3–P2O5–SrO–Ta2O5 glass system using Monte Carlo ...
Farzad. Isazadeh, Akbar. Abdi Saray
semanticscholar   +1 more source

MCNPX Model/Table Comparison [PDF]

open access: yes, 2003
MCNPX is a Monte Carlo N-Particle radiation transport code extending the capabilities of MCNP4C. As with MCNP, MCNPX uses nuclear data tables to transport neutrons, photons, and electrons. Unlike MCNP, MCNPX also uses (1) nuclear data tables to transport protons; (2) physics models to transport 30 additional particle types (deuterons, tritons, alphas ...
openaire   +2 more sources

Home - About - Disclaimer - Privacy