scholarly journals Estimation and Calibration of Thermal Neutron Flux for Neutron Activation Analysis

2006 ◽  
Vol 27 (12) ◽  
pp. 2061-2063 ◽  
1969 ◽  
Vol 23 (2) ◽  
pp. 121-124 ◽  
Author(s):  
W. H. Strain ◽  
C. G. Rob ◽  
W. J. Pories ◽  
R. C. Childers ◽  
M. F. Thompson ◽  
...  

Normal and atherosclerotic aortas from rats and man have been analyzed by neutron activation to determine changes in the content of Ca, Cd, Co, Cu, Mg, Mn, Se, V, and Zn with the development of degenerative changes. Samples of aortic tissue were weighed, dried at 110°C overnight, and irradiated for 30 min in a thermal neutron flux of 1.8X1012 n/cm2-sec in a TRIGA Mark I reactor. Immediately after irradiation, the samples were wet-ashed in the presence of carriers, the various elements were then radiochemically separated, and the separated fractions were counted by multichannel gamma-ray spectrometry. Definite values, or firm upper limits, for the elements were calculated by computer. With increasing degree of atherosclerosis, the Ca content rose from <350 to 36 000±2000 ppm; Co from undetectable to 0.34 ppm; Mg from <110 to 880 ppm; Mn from 0.34 to 1.26 ppm; and Zn from 37 to 152 ppm. Significant changes could not be detected in Cd, Se, and V; changes in Cu were not consistent. These results are discussed in relation to the pathological changes and to zinc therapy in the treatment of atherosclerosis.


2013 ◽  
Vol 101 (9) ◽  
pp. 601-606
Author(s):  
M. Wasim

Summary Miniature neutron source reactors (MNSR) are known for their stable neutron flux characteristics and are mostly employed for neutron activation analysis (NAA). Interfering reactions are sometimes observed in instrumental neutron activation analysis (INAA). Failure to correct for these interferences produces significant systematic positive errors. This paper provides correction factors for the interferences caused by the threshold reactions and fission products of 235U. These factors were calculated by using the experimentally determined thermal, epithermal and fast neutron flux and epithermal neutron flux shape factor and the nuclear data from the literature using the Høgdahl convention. Correction factors were calculated for (n, p) and (n, α) reactions for the most commonly observed radionuclides in INAA. Similarly, correction factors for uranium fission were calculated for 9 elements (Ce, Ba, La, Mo, Nd, Pd, Ru, Sm and Zr). The correction factors were validated by analyzing different materials. A comparison of uranium fission factors with those published in the literature showed a good agreement except for 97Zr, 99Mo and 131Ba which is due to difference in the flux characteristics. In general, these factors can be used with confidence.


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