Fast-neutron/gamma-ray radiography scanner for the detection of contraband in air cargo containers

Author(s):  
J. Eberhardt ◽  
Y. Liu ◽  
S. Rainey ◽  
G. Roach ◽  
B. Sowerby ◽  
...  
2007 ◽  
Author(s):  
Brian Sowerby ◽  
J. E. Eberhardt ◽  
A. J. McEwan ◽  
D. Milinkovic ◽  
V. Sharp ◽  
...  

2005 ◽  
Vol 63 (2) ◽  
pp. 179-188 ◽  
Author(s):  
J.E. Eberhardt ◽  
S. Rainey ◽  
R.J. Stevens ◽  
B.D. Sowerby ◽  
J.R. Tickner

2007 ◽  
Author(s):  
Brian Sowerby ◽  
J. E. Eberhardt ◽  
Y. Liu ◽  
S. Rainey ◽  
G. J. Roach ◽  
...  

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.


1999 ◽  
Author(s):  
D. Vartsky ◽  
M. B. Goldberg ◽  
G. Engler ◽  
A. Goldschmidt ◽  
G. Feldman ◽  
...  

2017 ◽  
Vol 2017 ◽  
pp. 1-9 ◽  
Author(s):  
Shams A. M. Issa ◽  
M. I. Sayyed ◽  
M. H. M. Zaid ◽  
K. A. Matori

The WinXCom program has been used to calculate the mass attenuation coefficients (μm), effective atomic numbers (Zeff), effective electron densities (Nel), half-value layer (HVL), and mean free path (MFP) in the energy range 1 keV–100 GeV for Gd3Al2Ga3O12Ce (GAGOC) and CaMoO4 (CMO) scintillator materials. The geometrical progression (G-P) method has been used to compute the exposure buildup factors (EBF) and gamma ray energy absorption (EABF) in the photon energy range 0.015–15 MeV and up to a 40 penetration depth (mfp). In addition, the values of the removal cross section for a fast neutron ∑R have been calculated. The computed data observes that GAGOC showed excellent γ-rays and neutrons sensing a response in the broad energy range. This work could be useful for nuclear radiation sensors, detectors, nuclear medicine applications (medical imaging and mammography), nuclear engineering, and space technology.


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