ISO 7097-1:2004
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
- Статус документа:
- Отменён
- Формат:
- Электронный (PDF)
- Количество страниц:
- 14
- Дата публикации:
- 21 июля 2004 г.
- Издание:
- ISO IS 7097 edition 1 version 1
- ICS:
- 27.120.30
ISO 7097-1:2004 describes an analytical method for the determination of uranium in pure product material samples such as U metal, UO2, UO3, uranyl nitrate hexahydrate, uranium hexafluoride and U3O8 from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability. This method can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or unirradiated, and of uranium nitrate product solutions. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere, and other elements which could cause interference are not normally present in sufficient quantity to affect the result significantly. The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of any alternative technique which could give equivalent performance. As the performance of some steps of the method is critical, the use of some automatic device has some advantages, mainly in the case of routine analysis.
Abstract
Overview
ISO 7097-1:2004 specifies a titrimetric analytical method for the determination of uranium in solutions, uranium hexafluoride and solids using an iron(II) reduction / potassium dichromate oxidation procedure. It covers assay of pure product materials from the nuclear fuel cycle - e.g., U metal, UO2, UO3, U3O8, uranyl nitrate hexahydrate and UF6 - and is suitable for nuclear materials accountability and quality control. The method uses mass titration to improve precision and a potentiometric end point for the dichromate titration.
Key topics and technical requirements
- Analytical principle: Reduce U(VI) to U(IV) with Fe(II) in concentrated phosphoric acid (with amidosulfuric acid to remove nitrite), oxidize excess Fe(II) with nitric acid catalysed by molybdenum, then titrate U(IV) with standardized potassium dichromate to a potentiometric end point. Vanadium(IV) is added to enhance kinetics and shift redox potential.
- Sample size and titration: Typical aliquot contains about 40–60 mg U in nitric-acid solution; method recommends mass titration for improved accuracy.
- Reagents and concentrations: Specifies analytical-grade reagents (HF, HNO3, H3PO4, FeSO4, amidosulfuric acid, vanadyl sulfate, and K2Cr2O7). Example: K2Cr2O7 solution ≈ 0.0085 mol·kg−1 and FeSO4 ≈ 1 mol·l−1; reagent stability and lot verification are required.
- Calibration & verification: Potassium dichromate solution must be standardized against internationally recognized uranium reference materials or NIST SRM 136 per ISO 10980.
- Interferences: Procedure is robust - common ions and many fission products (up to ~10% burn-up equivalent) do not significantly interfere. Specific interfering species (e.g., iodide/iodate, some platinum-group elements, As(III), Sb(III)) are identified and should be considered case-by-case.
- Quality considerations: Some steps are critical; automated devices can improve repeatability for routine analysis. Precision, repeatability and bias guidance are included.
Practical applications
- Routine uranium assay in nuclear fuel production and reprocessing facilities.
- Material accountancy and safeguards measurements for uranium product streams and fuel pellets.
- Quality control for uranium compounds (UO2 powder, U metal, UF6, uranyl nitrate) and validation of analytical laboratories performing redox titrations.
- Method selection where potentiometric end points and traceable calibration to certified reference materials are required.
Who uses this standard
- Nuclear fuel manufacturers and fabrication labs
- Radiochemical and analytical chemistry laboratories
- Regulatory and safeguards organizations responsible for nuclear materials accountancy
- Metrology institutes and laboratories validating uranium reference materials
Related standards
- ISO 7097-2 (iron(II) reduction / cerium(IV) oxidation titrimetric method)
- ISO 9894 (subsampling of UF6 in liquid phase)
- ISO 10980 (validation of strength of reference solutions)
Keywords: ISO 7097-1, uranium determination, potassium dichromate titration, iron(II) reduction, nuclear fuel technology, uranium assay, potentiometric titration, nuclear materials accountability.
Технические детали
- Технический комитет
- ISO/TC 85/SC 5 - Nuclear installations, processes and technologies
- SKU
- ISO 7097-1:2004
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