Determination of the Radionuclide Composition of the Cesium-Strontium Fraction of High-Level Waste from Spent Nuclear Fuel Reprocessing

被引：0
|
作者：
Chukhlantseva, E. V. [1 ]
Stepanova, O. V. [1 ]
Dichenko, O. Yu. [1 ]
Kutuzova, O. A. [1 ]
Dzhevello, K. A. [1 ]
Tatarnikova, Yu. M. [1 ]
Demchenko, E. A. [1 ]
Borisenko, V. P. [1 ]
机构：
[1] Mayak Prod Assoc, Ozyorsk 456780, Chelyabinsk, Russia
来源：
RADIOCHEMISTRY | 2024年 / 66卷 / 06期
关键词：
spent nuclear fuel; radionuclide composition; short-lived fraction; liquid scintillation spectrometry; inductively coupled plasma mass spectrometry; alpha-ray spectrometry; beta-ray spectrometry; gamma-ray spectrometry; SEPARATION; SAMPLES;
D O I：
10.1134/S1066362224060146
中图分类号：
O65 [分析化学];
学科分类号：
070302 ; 081704 ;
摘要：
Procedures were developed for measuring and calculating the radionuclide composition of the cesium-strontium fraction of radioactive waste from spent nuclear fuel reprocessing. The optimum conditions for recovering specific components and separating them from components interfering with their determination were found. The content of the following controlled radionuclides was determined experimentally: C-14, Sr-90, Tc-99, Sn-126, I-129, Cs-135,Cs-137, U-234-236,U-238, Pu238-242, Np-237, Am-241,Am-243, and Cm244-246. The content of Ni-63, Zr-93, Nb-94, Sm-151, and (242)mAm was determined by calculations. The radionuclide composition was determined in the solution before solidification of the cesium-strontium fraction. The composition of the solidified cesium-strontium fraction in the form of the borosilicate glass was determined by the calculation from the activity concentrations of the radionuclides in the solution before solidification and process characteristics (solution volume, glass frit weight, separation factors, and factors of incorporation into the glass).
引用
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页码：890 / 900
页数：11
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