scholarly journals Determination of relative and absolute efficiency functions in the range of 122 keV ÷ 8.5 MeV of HPGe detector

2015 ◽  
Vol 18 (2) ◽  
pp. 79-87
Author(s):  
Son An Nguyen ◽  
Lanh Dang ◽  
Minh Van Truong
Keyword(s):  
Quantitative Analysis ◽  
Neutron Activation ◽  
Point Source ◽  
Energy Range ◽  
Hpge Detector ◽  
Nuclear Reactor ◽  
Absolute Efficiency ◽  
Gamma Sources ◽  
Reaction 35Cl

Construction of detector is necessary. However, on large energy range the manufacturers could not also support the explicit function of relative and absolute efficiencies of detectors. One of the reasons is a restriction of energy range of gamma sources (normally < 3 MeV). This paper presents the results of construction of relative and absolute efficiency functions within a range from 122 keV to 8.5 MeV. The sources are used combining 152Eu point source and 36Cl activated isotope by thermal neutron captured reaction 35Cl of Dalat nuclear reactor (DNR) by 35Cl(n, γ)36Cl reaction. This result can be applied in determining quantitative analysis of samples of neutron activation and radioactivity chemistry

scholarly journals DETERMINATION OF CONTENT OF SOME ELEMENTS IN THE HUMAN BLOOD BY METHOD OF INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS USING DALAT NUCLEAR REACTOR

2011 ◽  
Vol 14 (1) ◽  
pp. 47-54
Author(s):  
Hung Van Nguyen
Keyword(s):  
Neutron Activation Analysis ◽  
Instrumental Neutron Activation Analysis ◽  
Activation Analysis ◽  
Neutron Activation ◽  
Human Blood ◽  
Nuclear Reactor ◽  
Gamma Spectrometer ◽  
Standard Samples ◽  
Instrumental Neutron Activation

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.

Determination of efficiency of an aged HPGe detector for gaseous sources by self absorption correction and point source methods

2017 ◽  
Vol 12 (07) ◽  
pp. T07006-T07006 ◽  
Author(s):  
R. Sarangapani ◽  
M.T. Jose ◽  
T.K. Srinivasan ◽  
B. Venkatraman
Keyword(s):  
Point Source ◽  
Hpge Detector ◽  
Absorption Correction

scholarly journals Determination of the neutron beam diameter based on the neutron activation analysis

2016 ◽  
Vol 19 (4) ◽  
pp. 147-153
Author(s):  
Son An Nguyen ◽  
Tien Van Dang ◽  
Thang Huu Ho ◽  
Hieu Bao Quoc Phan
Keyword(s):  
Neutron Activation Analysis ◽  
Activation Analysis ◽  
Neutron Activation ◽  
Neutron Beam ◽  
Nuclear Reactor ◽  
Nuclear Research ◽  
Beam Diameter ◽  
Analysis Errors ◽  
Reduced Data

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].

Development of a Technique for the Calibration of HPGe Detector to Estimate Radionuclides Present in Steel Samples

2013 ◽  
Vol 794 ◽  
pp. 766-770
Author(s):  
Sarbjit Singh ◽  
Amol Mhatre
Keyword(s):  
Point Source ◽  
Hpge Detector ◽  
Environmental Safety ◽  
Point Sources ◽  
Efficiency Calibration ◽  
Detector System ◽  
Steel Disk ◽  
System A ◽  
Disk Sample

The quantitative assay of radionuclides present in steel samples is required for the environmental safety as well as in the process control and quality control of the finished products. The standard sources should also be prepared in the required size and shape as that of the sample, for the efficiency calibration of the HPGe detector system. A method was developed and tested to use 152Eu point source for the determination of efficiency of an extended steel disk source using HPGe detector system. Standard point sources of 152Eu were prepared by transferring known amount of 152Eu activity by weight. Standard steel disk sources of required dimensions were also prepared by distributing uniformly the standard activity of 152Eu on both sides of the inactive steel disk. The extrapolated efficiency of the steel disk sample was determined using the efficiency of the 152Eu point source and it was compared with the efficiency determined using the standard sources of 152Eu prepared on the steel disks. The two efficiency calibration curves matched very well within the experimental limits. Using this efficiency calibration, a few steel samples were analyzed for the radionuclides present in them. The detections limits for most of the nuclides were much less than the specified limits. The method can further be extended for other types of geometries with suitable modifications for the changes in thickness and attenuation corrections.

MEASUREMENT OF GERMANIUM ESCAPE PEAKS IN PIXE SPECTRA RECORDED USING HIGH PURITY Ge (HPGe) DETECTOR

2009 ◽  
Vol 19 (01n02) ◽  
pp. 67-76
Author(s):  
SANJIV KUMAR ◽  
G. L. N. REDDY ◽  
V. S. RAJU
Keyword(s):  
Quantitative Analysis ◽  
High Purity ◽  
Hpge Detector ◽  
X Rays ◽  
Pixe Analysis ◽  
Escape Peak ◽  
X Ray ◽  
High Purity Germanium ◽  
Experimental Values

This paper deals with studies on Ge K α and K β escape peaks in particle induced X-ray emission (PIXE) spectra recorded by a high purity germanium (HPGe) detector. A knowledge of the energies and intensities of these escape peaks is desirable for accurate qualitative as well as quantitative analysis of elements by PIXE. The spectral interferences caused by Ge K escape peaks in the determination of Fe in U by PIXE are highlighted for illustration. A simple theoretical approach based on the production of Ge K X-rays inside the Ge crystal of the detector during the process of detection of the incident characteristic X-rays and the subsequent escape of a fraction of the produced radiations from the crystal, is described to calculate the intensity ratio of the Ge escape peak to its parent characteristic X-rays. The calculated values are in agreement with the experimental values and those estimated using the formulation provided in GUPIX software for PIXE. The Ge K escape peaks are very prominent; the intensities of Ge K α escape peaks, from bromine to silver, range from 15% to 6% of those of their respective K α X-rays. These intensities are, in general, considerably higher compared to those of Si escape peaks in spectra recorded by Si ( Li ) detector. Ge K escape peaks therefore may give rise to severe interferences. The present approach provides a precise (~8%) determination of the intensity of an escape peak and thereby facilitates a reliable PIXE analysis.

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