An Analysis of Total Gamma Ray Cross Sections in the Energy Region from 40 to 80 keV in Cu, Sn, W, and Pb

1969 ◽  
Vol 22 (1) ◽  
pp. 131
Author(s):  
M Raja Rao ◽  
K Parthasaradhi
Keyword(s):  
Cross Sections ◽  
Energy Region ◽  
Gamma Ray

In Table 1 the values of the experimental total y-ray cross sections measured by Wiedenbeck (1962), Bearden (1966), Knerr and Vonach (1967), and McCrary et al. (1967) at energies of 40,50, 60, 70, and 80 keY in the elements Cu, Sn, W, and Pb are given. It will be seen that in Cu at 80 keY, in Sn at 40 keY, in W at 50 keY, and in Pb at 40, 50, and 70 ke V these values do not agree well amongst themselves, even after considering the error limits.

scholarly journals A Comprehensive Study on Gamma-Ray Exposure Build-Up Factors and Fast Neutron Removal Cross Sections of Fly-Ash Bricks

2013 ◽  
Vol 2013 ◽  
pp. 1-13 ◽  
Author(s):  
Vishwanath P. Singh ◽  
N. M. Badiger
Keyword(s):  
Fly Ash ◽  
Fast Neutron ◽  
Photon Energy ◽  
Cross Sections ◽  
Energy Region ◽  
Gamma Ray ◽  
Region Of Interest ◽  
Chemical Compositions ◽  
Shielding Effectiveness ◽  
Penetration Depths

Geometric progression (GP) method was utilized to investigate gamma-ray exposure build-up factors of fly-ash bricks for energies from 0.015 to 15 MeV up to 40 mfp penetration depth. The EBFs of the fly-ash bricks are dependent upon the photon energy, penetration depths, and the chemical compositions of the elements. Appreciable variations in exposure build-up factor (EBF) are noted for the fly-ash bricks. The EBFs were found to be small in low and high photon energy regions whereas very large in medium energy region. EBF of the bricks is inversely proportional to equivalent atomic number below 10 mfp for entire energy region of interest 0.015 to 15 MeV. The EBFs of fly-ash, brick of mud, and common brick were similar at 1.5 MeV photon energy. The EBF of the fly-ash bricks was found to be higher than that of the brick of mud, and common brick. The fast neutron removal cross sections of the fly-ash bricks, brick of mud, and common bricks were also calculated which were found to be in the same order. It is expected that this study should be very directly useful for shielding effectiveness of fly-ash brick materials and dose estimation.

Measurement of Intermediate Energy Gamma-Ray Cross Sections

1971 ◽  
Vol 49 (9) ◽  
pp. 1167-1178 ◽  
Author(s):  
L. C. Henry ◽  
T. J. Kennett
Keyword(s):  
Pair Production ◽  
Production Process ◽  
Cross Section ◽  
Cross Sections ◽  
Energy Region ◽  
Gamma Ray ◽  
Intermediate Energy ◽  
Energy Gamma ◽  
Pair Production Process ◽  
Better Than

Gamma-ray cross sections for 30 well-distributed energies from 121 keV to 10.827 MeV in 9 target elements ranging from carbon to uranium have been measured with an accuracy of better than 1%. Deviations from recently quoted theoretical cross sections were observed in the energy region from 6–11 MeV, particularly for high-Z target materials. The approximately Z2 dependent deviations are certainly associated with the elastic pair-production process, the present opinion being that they arise from an overestimation of the effects of atomic–electron screening on the pair cross section in the intermediate energy region.

Total Gamma-Ray Cross Sections in the Energy Region 60-1400 keV

1973 ◽  
Vol 7 (3) ◽  
pp. 1001-1003 ◽  
Author(s):  
K. Sivasankara Rao ◽  
B. V. Thirumala Rao ◽  
B. Mallikarjuna Rao ◽  
V. Visweswara Rao ◽  
K. Parthasaradhi
Keyword(s):  
Cross Sections ◽  
Energy Region ◽  
Gamma Ray

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Effective Neutron ◽  
Simulation Codes

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.

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