Neutron activation analysis for determination of induced radioactivity in concrete of nuclear reactor shielding

1989 ◽  
Vol 131 (2) ◽  
pp. 261-270 ◽  
Author(s):  
P. A. Lavdanskij ◽  
V. M. Nazarov ◽  
N. I. Stefanov ◽  
M. V. Frontasyeva
2011 ◽  
Vol 14 (1) ◽  
pp. 47-54
Author(s):  
Hung Van Nguyen

Neutron activation analysis using nuclear reactor has been used widely to determine of content of elements in environment, biology, geology, archaeology, etc. In this report, determination of content of some elements in the human blood by method of instrumental neutron activation analysis using Dalat nuclear reactor coupled with processing of results by k-zero method (using k0-Dalat code) and by relative one (using standard samples) is presented. 50 samples of the human blood are mainly collected from public objects in Lamdong province. They are prepared and activated together with the standard samples at the dry channel No. 7-1 and the rotary specimen rack (wet channel) of the reactor. Then they are directly measured by the HPGe gamma spectrometer and the measured data are processed. The experimental results for determination of ranges of contents and average values for 8 elements respectively are Na (1.06 - 2,48; 1.71 ± 0.30 mg/ml), Cl (1.10 - 3.75; 2.66 ± 0.71 mg/ml), Fe (0.26 - 0.72; 0.49 ± 0.09 mg/ml), K (0.31 - 1.14; 0.73 ± 0.15 mg/ml), Zn (4.55 - 13.97; 8.08 ± 1.24 μg/ml), Rb (2.73 - 7.92; 5.11 ± 0.86 μg/ml), Se (0.04 - 0.18; 0.08 ± 0.03 μg/ml) and Sc (0.22 – 1.61; 0.56 ± 0.24 ng/ml). Besides, content of sodium to be determined by the k-zero method and the relative one are compared also. The results for determination of contents of 8 elements in the human samples to be compared with those of other authers are shown that this method has had confidence, and it could be applied routinely in determination of contents of multi-elements.


2016 ◽  
Vol 19 (4) ◽  
pp. 147-153
Author(s):  
Son An Nguyen ◽  
Tien Van Dang ◽  
Thang Huu Ho ◽  
Hieu Bao Quoc Phan

Neutron beam diameter is a very important parameter in the experimental nuclear research. Determination of the correct neutron beam diameter is the best method to prepare corectly the optimal sample size correctly, reduced data analysis errors. To measure the neutron diameter, some methods were used: Simulation by Monte – Carlo method, neutron image, and neutron activation analysis. In this report, we determined the neutron beam diameter of the 3rd horizontal channel of the Dalat nuclear reactor that activated gold foils. The result shows that this method offer quick and more correct results than other methods which had been published preiously [1, 2].


Fuel ◽  
1975 ◽  
Vol 54 (1) ◽  
pp. 70-71 ◽  
Author(s):  
Charles E. Hamrin ◽  
Peter S. Maa ◽  
Lindgren L. Chyi ◽  
William D. Ehmann

Sign in / Sign up

Export Citation Format

Share Document