Monte Carlo Solutions for Selected Problems in Gamma-Ray Spectrometry and Nuclear Activation Analysis

2008 ◽  
Author(s):  
Octavian Sima ◽  
Emanuela Cincu ◽  
Ioana Manea ◽  
Mike Woods
2006 ◽  
Vol 71 (7) ◽  
pp. 1042-1050
Author(s):  
Manju Tandon ◽  
Piyush Kumar ◽  
Haiyan Xia ◽  
Lili Wang ◽  
Leonard I. Wiebe

A rapid PCB-screening protocol, based on a combination of extraction techniques and instrumental nuclear activation analysis (INAA), required water soluble brominated internal standard that undergoes facile hydrolysis to a lipophilic brominated counterpart. Bromophenyl glucuronic acids 2, 3, 7 were synthesized for this application. Glucuronic acids 2 and 3 were prepared by bromination of phenyl β-D-glucopyranosiduronic acid in 81 and 54%, respectively, whereas compound 7 was prepared by coupling methyl 2,3,4-tri-O-acetyl-α-D-glucopyranosyluronate bromide (5) with 2,4,6-tribromophenol. Incubation with β-glucuronidase indicated that tribromophenyl derivative 7 is an excellent substrate, with near quantitative conversion to tribromophenol within seconds of incubation with the enzyme.


Maturitas ◽  
1992 ◽  
Vol 15 (3) ◽  
pp. 256
Author(s):  
J. Kalef-Ezra ◽  
D. Glaros ◽  
G. Klouvas ◽  
J. Hatzikonstantinou ◽  
A. Karantanas ◽  
...  

2021 ◽  
Author(s):  
David Breitenmoser

<p>The objective of this work is to simulate the spectral gamma-ray response of NaI(Tl) scintillation detectors for airborne gamma-ray spectrometry (AGRS) using Monte Carlo radiation transport codes. The study is based on a commercial airborne gamma-ray spectrometry detector system with four individual NaI(Tl) scintillation crystals and a total volume of 16.8 l. Monte Carlo source-detector simulations were performed in an event-by-event mode with the commercial multi-purpose transport codes MCNP6.2 and FLUKA. Validation measurements were conducted using <sup>241</sup>Am, <sup>133</sup>Ba, <sup>60</sup>Co, <sup>137</sup>Cs and <sup>152</sup>Eu radiation sources with known activities and source-detector geometries. Energy resolution functions were derived from these measurements combined with additional measurements of natural Uranium, Thorium and Potassium sources. The simulation results are in good agreement with the experimental data with a maximum relative error in the full-energy peak counts of 10%. In addition, no significant difference between the two Monte Carlo radiation transport codes was found with respect to a 95% confidence level. The validated detector model presented herein can be adopted for angular detector response analysis and calibration computations relating radionuclide activity concentrations with spectral detector counts.</p>


1965 ◽  
Vol 48 (6) ◽  
pp. 1139-1147
Author(s):  
H L Schlesinger ◽  
M J Pro ◽  
C M Hoffman ◽  
M Cohan

Abstract Activation analysis has been employed to compare and determine the source of manufacture of drugs. The irradiations were carried out with the DASA-TRIGA1 and Naval Research Laboratory nuclear reactors,2 and the induced radionuclides were identified by nondestructive gamma-ray spectrometry. The results show that the technique can be a useful tool for the identification of trace elements which serve to characterize drugs.


1967 ◽  
Vol 50 (2) ◽  
pp. 371-376
Author(s):  
J E Scott ◽  
C M Hoffman ◽  
M J Pro ◽  
H L Schlesinger

Abstract Adhesive tapes were compared by nondestructive gamma-ray spectrometry. Results show that neutron activation analysis can he used to characterize tapes through their elemental composition. Differences between manufacturers as well as hatch-tobatch and in-batch variations can be measured by neutron activation analysis.


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