Results 101 to 110 of about 4,949 (201)

A comprehensive study of the energy absorption and exposure buildup factors of different bricks for gamma-rays shielding

Results in Physics, 2017
The present investigation has been performed on different bricks for the purpose of gamma-ray shielding. The values of the mass attenuation coefficient (µ/ρ), energy absorption buildup factor (EABF) and exposure buildup factor (EBF) were determined and ...
M.I. Sayyed, M.Y. AlZaatreh, M.G. Dong, M.H.M. Zaid, K.A. Matori, H.O. Tekin   +5 more
doaj   +1 more source

Photon and neutron shielding performance of boron phosphate glasses for diagnostic radiology facilities

Results in Physics, 2019
This study focuses on radiation shielding characteristics of Li2O, Al2O3 and ZnO-doped boron phosphate glasses containing PbO and Bi2O3. Mass attenuation coefficient (μ/ρ) values of the glasses have been calculated using MCNPX code at various photon ...
H.O. Tekin, E.E. Altunsoy, E. Kavaz, M.I. Sayyed, O. Agar, M. Kamislioglu   +5 more
doaj   +1 more source

Residual nuclide formation in 206,207,208,nat-Pb and 209-Bi induced by 0.04-2.6 GeV Protons as well as in 56-Fe induced by 0.3-2.6 GeV Protons

, 2007
5972 independent and cumulative yields of radioactive residuals nuclei have been measured in 55 thin 206,207,208,nat-Pb and 209-Bi targets irradiated by 0.04, 0.07, 0.10, 0.15, 0.25, 0.6, 0.8, 1.2, 1.4, 1.6, and 2.6 GeV protons.
Batyaev, V. F., Butko, M. A., Florya, S. N., Gudowski, W., Ignatyuk, A. V., Mashnik, S. G., Pavlov, K. V., Tikhonov, R. S., Titarenko, A. Yu., Titarenko, Yu. E.   +9 more
core   +1 more source

Comparative analysis of MCNPX and GEANT4 codes for fast-neutron radiation treatment planning

Nuclear Energy and Technology, 2015
AbstractThe paper presents a comparative analysis of the MCNPX and GEANT4 simulation tools for the beam therapy fast neutron transport calculation problems. Groups of model experiments are described which compare the absorbed energy calculated values obtained on different types of phantoms and the rate of calculation for both simulation tools is ...
A.N. Solovyev, V.V. Fedorov, V.I. Kharlov, U.A. Stepanova   +3 more
openaire   +2 more sources

Fast Neutron Detection with a Segmented Spectrometer

, 2014
A fast neutron spectrometer consisting of segmented plastic scintillator and He-3 proportional counters was constructed for the measurement of neutrons in the energy range 1 MeV to 200 MeV.
Bass, C. D., Beise, E. J., Breuer, H., Erwin, D. K., Heimbach, C. R., Langford, T. J., Nico, J. S.   +6 more
core   +1 more source

Assessment of MCNPX Monte Carlo Code for Absorbed Dose Calculations in Mammogarphy Examination

Afyon Kocatepe University Journal of Sciences and Engineering, 2017
Introduction: This study aimed to investigate capabities of MCNPX monte carlo code for calculations of average absorbed dose in a breast phantom during mammography examination. Also, the effect of tube voltage and breast thickness on absorbed dose was determined by using Monte carlo method.
MANİCİ, Tugba, KARA, Ümit, SİNGH, Viswanath P, MESBAHI, ASGHAR, ALTUNSOY, E Ebru, TEKİN, HÜSEYİN OZAN   +5 more
openaire   +4 more sources

HIZLANDIRICI GÜDÜMLÜ SİSTEMLERDE BAZI UZUN ÖMÜRLÜ NÜKLEER ATIKLARIN DÖNÜŞÜMÜNÜN İNCELENMESİ

Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2009
Özet: Bu çalışmada Hızlandırıcı Güdümlü Sistem (ADS) kullanılarak uzun yarı ömürlü 99Tc, 129I, 237Np, 238U ve 239Pu nükleer atıkların kararlı veya kısa yarı ömürlü izotoplara dönüşümleri incelenmiştir. Bunun için sırasıyla 1, 2 ve 3 GeV enerjili ve 10 mA
Mehmet Emin KORKMAZ
doaj  

Measurement and calculation of neutron energy spectrum in TRR irradiation facilities: a feasibility study of using TRR for BNCT [PDF]

مجله علوم و فنون هسته‌ای, 2015
An investigation has been made for the use of Tehran Research Reactor (TRR) as a neutron source for the boron neutron capture therapy (BNCT) by calculating and measuring the energy spectrum and spatial distribution of neutrons in all external irradiation
Yaser kasesaz, Hossein Khalafi, Faezeh Rahmani, Arsalan Ezati, Ashkan Hosnirokh, Mehdi Keyvani   +5 more
doaj  

A Comparison between GATE and MCNPX monte carlo codes in simulation of medical linear accelerator

Journal of Medical Signals & Sensors, 2014
Radiotherapy dose calculations can be evaluated by Monte Carlo (MC) simulations with acceptable accuracy for dose prediction in complicated treatment plans. In this work, Standard, Livermore and Penelope electromagnetic (EM) physics packages of GEANT4 application for tomographic emission (GATE) 6.1 were compared versus Monte Carlo N-Particle eXtended ...
Hamid-Reza, Sadoughi, Shahrokh, Nasseri, Mahdi, Momennezhad, Hamid-Reza, Sadeghi, Mohammad-Hossein, Bahreyni-Toosi   +4 more
openaire   +2 more sources

Investigation of spherical and cylindrical catural Iridium targets by photonuclear reaction

EPJ Web of Conferences, 2017
In this study, natural iridium consisting of Ir-191 and Ir-193 isotopes has been irradiated with 21 MeV photons. The distribution of photons, electrons and neutrons fluxes in the spherical and cylindrical natural iridium target have been calculated using
Korkmaz Mehmet Emin, Agar Osman, Yigit Mustafa   +2 more
doaj   +1 more source