Open AccessEstimation of Accuracy of the Method of Gamma- Spectrometry for Non-Destructive Control of Gadolinium Content and Uranium Enrichment in Non-Irradiated VVER-type Fuel Pellets
Author(s) -
Yu. V. Stogov
Publication year - 2020
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1689/1/012060
Subject(s) - pellets , analytical chemistry (journal) , gadolinium , content (measure theory) , uranium , materials science , thorium , chemistry , radiochemistry , chromatography , mathematical analysis , mathematics , metallurgy , composite material
The gamma-spectra of the single (UO 2 -Gd 2 O 3 )-pellets were measured on the planar detector HPLeGe. The measurements of Gd content in (UO 2 -Gd 2 O 3 )-pellets were performed by X-ray fluorescence method. The total count rate in the doublet 42,3 and 43,0 keV K α 1,2 -X-rays from Gd was used as a measure of Gd content. In measurements was used 241 Am as an external radiation source for exciting the doublet 42,3 and 43,0 keV K α 1,2 -X-rays from Gd. In order to obtain the calibration dependence of count rate in doublet 42,3 and 43,0 keV from Gd content in (UO 2 -Gd 2 O 3 )-pellets there were used standard (UO 2 -Gd 2 O 3 )-pellets with the known Gd content, density and enrichment. The estimates of influence of deviations of the density of (UO 2 -Gd 2 O 3 )-pellets and Gd content on total count rate in doublet 42,3 and 43,0 keV were performed. The “pure” gamma-spectra (without employing of external radiation source) were used to obtain the data on uranium enrichment of fuel pellets using multigroup gamma-spectra analysis code (MGAU) and additional information about Gd content. The dependence of S 185 , 7 k e V S 98 , 43 k e V from Gd content in (UO 2 -Gd 2 O 3 )-pellets is present (the ratio of count rates for two peaks: E γ =185,7 keV (the measure of 235 U) and E=98,43 keV (the measure of 235,238 U).