Fast neutron damage of a pixelated CdZnTe gamma ray spectrometer

Author(s):  
Y. Eisen ◽  
A. Shor
2016 ◽  
Vol 5 (03) ◽  
pp. 4892 ◽  
Author(s):  
Ratna Raju M.* ◽  
Madhusudhana Rao P. V. ◽  
Seshi Reddy T. ◽  
Raju M. K. ◽  
Brahmaji Rao J. S. ◽  
...  

A study was undertaken to evaluate the inorganic elements for humans in two Indian medicinal plants leaves, namely Sphaeranthus indicus, and Cassia fistula by Instrumental Neutron Activation Analysis (INAA). INAA experiment was performed by using 20 kW KAMINI Reactor at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam. The emitted gamma rays were measured using gamma ray spectrometer. The concentrations of Al, Br, Ca, Fe, K, La, Mg, Mn, Na, Sc, V and Zn were determined in the selected medicinal plants. The medicinal leaves are using in treatment of various important ailments. The elemental content in selected medicinal leaves is various proportions depending on the soil composition, location of plant specimen and the climate in which the plant grows.


2020 ◽  
Vol 91 (10) ◽  
pp. 104707
Author(s):  
Yinyu Liu ◽  
Hao Xiong ◽  
Chunhui Dong ◽  
Chaoyang Zhao ◽  
Quanfeng Zhou ◽  
...  

2021 ◽  
Vol 92 (4) ◽  
pp. 043537
Author(s):  
M. Nocente ◽  
T. Craciunescu ◽  
G. Gorini ◽  
V. Kiptily ◽  
M. Tardocchi ◽  
...  

1977 ◽  
Vol 24 (1) ◽  
pp. 673-677 ◽  
Author(s):  
J. J. Lipsett ◽  
I. L. Fowler ◽  
R. J. Dinger ◽  
H. L. Malm

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.


Sign in / Sign up

Export Citation Format

Share Document