Activity Estimation of Gamma-Ray Emitting Sources Without the Preliminary Knowledge on a Shielding Design. Simulation and Experiment for NAI(TL) Detector

Author(s):  
Serguei Korneyev
2006 ◽  
Vol 26 (3) ◽  
pp. 301-308
Author(s):  
Xiangdong Xie ◽  
Guoshan Yang ◽  
Hongmei Zhou ◽  
Decheng Qu

2014 ◽  
Vol 29 (2) ◽  
pp. 149-156 ◽  
Author(s):  
Vishwaanath Singh ◽  
Nagappa Badiger

Shielding of a reactor is required for protection of people and environment during normal operation and accidental situations. In the present paper we investigated the shielding parameters viz. mass attenuation coefficients, linear attenuation coefficients, tenth-value layer, effective atomic numbers, kerma relative to air and exposure buildup factors for gamma-ray for ordinary, heavy, and super heavy concretes. Macroscopic effective removal cross-sections for fast neutron had also been calculated. Ordinary concrete is economically suitable for mixture high energy gamma-ray and neutron as it has large weight fraction of low-Z as compared with super heavy concretes to slow down the neutron. Super heavy concretes are superior shielding for both reactor operation and accident situations. The study is useful for optimizing for shielding design and radiation protection in the reactors.


OALib ◽  
2020 ◽  
Vol 07 (07) ◽  
pp. 1-6
Author(s):  
Maolin Xiong ◽  
Jin Yang ◽  
Xian Guan

2021 ◽  
Vol 16 (09) ◽  
pp. P09013
Author(s):  
Q.X. Zhang ◽  
M.L. Xiong ◽  
J. Zhang ◽  
L.Q. Ge ◽  
J. Yang ◽  
...  

2019 ◽  
Vol 6 (0) ◽  
pp. 48-51 ◽  
Author(s):  
Takeo Nishitani ◽  
Kunihiro Ogawa ◽  
Hiroki Kawase ◽  
Neng Pu ◽  
Tetsuo Ozaki ◽  
...  

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