scholarly journals A review of nuclear data for the k₀-based neutron activation analysis

2019 ◽  
Vol 9 (1) ◽  
pp. 28-33
Author(s):  
Manh Dung Ho ◽  
Lathdavong Phonesavanh

Nuclear data for the k0-based neutron activation analysis (k0-NAA) including: k0-factors – combination of nuclear constants (atomic mass, isotopic abundance, gamma-ray yield and thermal neutron capture cross section); Q0 – the ratio of the resonance integral to thermal neutron capture cross section; and Er – effective resonance energy, along with the related nuclear data are presented and evaluated in the presentation. Accuracy and capability of k0-NAA depends considerably on the reliability of the above mentioned nuclear data. In general, the evaluation of nuclear data is essential and necessary in the field of nuclear science and technology, and this work is conducted by the nuclear data centers on the world as well as the research institutions where the nuclear data are usedfor R&D. Therefore, the evaluation of the nuclear data used in k0-NAA should also be performed so that some of data may no longer be appropriate should be redetermined. The evaluation of nuclear data in k0-NAA would contribute to the improvement of accuracy and reliability of the method, moreover, it would also contribute to the establishment a nuclear database in Vietnam in the future.

1953 ◽  
Vol 31 (3) ◽  
pp. 204-206 ◽  
Author(s):  
Rosalie M. Bartholomew ◽  
R. C. Hawkings ◽  
W. F. Merritt ◽  
L. Yaffe

The thermal neutron capture cross sections of Na23 and Mn55 have been determined using the activation method. The values are 0.53 ± 0.03 and 12.7 ± 0.3 barns respectively with respect to σAul97 = 93 barns. These agree well with recent pile oscillator results. The half-life for Mn56 is found to be 2.576 ± 0.002 hr.


1955 ◽  
Vol 33 (8) ◽  
pp. 457-465 ◽  
Author(s):  
R. E. Bell ◽  
R. L. Graham ◽  
L. Yaffe

The thermal neutron capture cross section of radioactive Au198 has been measured by the activation method as 26,000 ± 1200 barns, assuming 99 barns for the thermal neutron cross section of Au197. Metallic Au197 was bombarded in fluxes up to 9 × 1013 thermal neutrons cm.−2 sec.−1 to produce a mixture of Au198 and Au199 by the successive neutron capture reactions Au197(n, γ)Au198(n, γ)Au199. The ratio of the Au199 activity to Au198 activity so produced yields σc(Au197). In a preliminary experiment, the half-life of Au199 was measured as 3.148 ± 0.010 days.


2007 ◽  
Author(s):  
T. Belgya ◽  
O. Bouland ◽  
G. Noguere ◽  
A. Plompen ◽  
P. Schillebeeckx ◽  
...  

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