Validation of gravimetry for high-accuracy analysis of uranium

被引：3

作者：

Ruas, Alexandre ^{[1
]}

Ben Messaoud, Warda ^{[1
]}

Rivier, Cedric ^{[1
]}

Solinhac, Isabelle ^{[1
]}

Le Roudil, Danie ^{[1
]}

机构：

[1] CEA, Radio Chem Processes Dept, Nucl Energy Div, F-30207 Bagnols Sur Ceze, France

来源：

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY | 2017年 / 311卷 / 03期

关键词：

Analysis; Gravimetry; Calcination; Uranium; Method validation; Uncertainty; THERMAL-DECOMPOSITION; URANYL-NITRATE; MEASUREMENT UNCERTAINTY; DEHYDRATION;

D O I：

10.1007/s10967-016-5116-7

中图分类号：

O65 [分析化学];

学科分类号：

070302 ; 081704 ;

摘要：

Gravimetry after calcination is an assay method for determining the quantity of a given element from the mass measurement. This method, adapted for high concentration and purity uranium solution, has the advantage of not being related to a chemical standard and of having an extremely high trueness and precision. Besides, the method is simple, robust and cost-effective. The results of the analytical method validation are shown. Expanded uncertainties, assessed thanks to a reference uranium nitrate solution, are lower than 0.2%. The technique can thus be used in addition to the well-known isotopic dilution thermal-ionisation mass-spectrometry.

引用

页码：1831 / 1838

页数：8

共 34 条

[1] Thermal ionisation mass spectrometry (TIMS) in nuclear science and technology - a review
Aggarwal, Suresh K.
[J]. ANALYTICAL METHODS, 2016, 8 (05) : 942 - 957
[2] [Anonymous], 1002008 JCGM
[3] [Anonymous], 7476 ISO
[4] [Anonymous], X15140 AFNOR FD
[5] [Anonymous], 1951, PART ELEMENT ITS BIN
[6] [Anonymous], 1012008 JCGM
[7] Boden RM, 1972, P S INT AT EN AG, P227
[8] Uranium and plutonium analysis of nuclear material samples by multi-collector thermal ionisation mass spectrometry: Quality control, measurement uncertainty, and metrological traceability
Buerger, S.
Balsley, S. D.
Baumann, S.
Berger, J.
Boulyga, S. F.
Cunningham, J. A.
Kappel, S.
Koepf, A.
Poths, J.
[J]. INTERNATIONAL JOURNAL OF MASS SPECTROMETRY, 2012, 311 : 40 - 50
[9] Chottard G, 1970, CEAR3717
[10] Monte Carlo simulation for the evaluation of measurement uncertainty of spent fuel analytical results
Crozet, Marielle
Rivier, Cedric
[J]. JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2014, 302 (01) : 103 - 115

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