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

页码：890 / 900

页数：11

共 26 条

[1]

[Anonymous], 1998, TU (Technical Specification) 52000-35: Uranium Dioxide with the Conventional Weight Fraction of Uranium-235 Isotope of up to 0.7%

[2]

[Anonymous], 2020, RB-093-20 Document: Safety Guide in Using Atomic Energy

[3]

[Anonymous], 1987, Measuring Extremely Low Levels of Alpha and Beta Activity, 1220 Quantulus

[4] Extraction chromatographic studies of metal ions using N,N,N′,N′-tetraoctyl diglycolamide as the stationary phase [J].

Ansari, SA ;

Pathak, PN ;

Husain, M ;

Prasad, AK ;

Parmar, VS ;

Manchanda, VK .

TALANTA, 2006, 68 (04) :1273-1280

[5]

Bogatov S.A., 2019, Vopr. Radiats. Bezopasn, V68, P39

[6] Assessment of Radioecologically Relevant Radionuclides 14C, 99Tc, and 129I in Vitrified High-Level Nuclear Wastes from Spent Fuel Reprocessing [J].

Chukhlantseva, E. V. ;

Stepanova, O. V. ;

Dichenko, O. Yu. ;

Zaitseva, T. A. ;

Dzhevello, K. A. ;

Murashova, E. L. ;

Tatarnikova, Yu. M. ;

Belanova, E. A. ;

Blokhin, P. A. .

JOURNAL OF ANALYTICAL CHEMISTRY, 2023, 78 (12) :1701-1711

[7]

Chukhlantseva E.V., Abstracts of Papers, 1-ya Shkola molodykh uchenykh "Nauchnye osnovy zavershayushchikh stadii yadernogo toplivnogo tsikla" (1st School of Young Scientists "Scientific Principles of the Back-End of the Nuclear Fuel Cycle"),, P59

[8]

Demin A.V., 1993, P 4 ANN SCI TECHN C

[9] Determination of 126Sn in radioactive waste using TEVAA® resin and gamma spectrometry [J].

Dulanska, Silvia ;

Bilohuscin, Jan ;

Remenec, Boris ;

Matel, L'ubomir ;

Darazova, L'ubica .

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2015, 304 (03) :1093-1097

[10] Application of extraction chromatography to the separation of thorium and uranium dissolved in a solution of high salt concentration [J].

Fujiwara, Asako ;

Kameo, Yutaka ;

Hoshi, Akiko ;

Haraga, Tomoko ;

Nakashima, Mikio .

JOURNAL OF CHROMATOGRAPHY A, 2007, 1140 (1-2) :163-167

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