A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry
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Raghbendra Thakur
und
Raj Ranjan Jha
Abstract
A novel and useful extraction spectrophotometric method for the rapid determination of uranium and free acidity in nuclear fuel process samples using the reagent, 2,3-dihydroxynaphthalene as an extractant as well as color forming agent is described. Uranium at milligram level forms a yellowish- orange anionic complex with the ligand, 2,3-dihydroxynaphthalene over a pH range, 10–12. This anionic complex is easily extracted into ethylacetate as an ion-pair complex with cetyltrimethylammonium cation (CTA+). The absorbance of the ion-pair complex in ethylacetate is measured at 390 nm. The molar absorptivity and Sandell’s sensitivity of the system being 5.0×103 L·mol−1 cm−1 and 0.047 μg cm−2, respectively at 390 nm. This very reagent (2,3-dihydroxynaphthalene) also forms a yellowish-orange nitro product with free nitric acid (HNO3) in the presence of concentrated sulfuric acid. This nitro- product is easily extracted into the same solvent (ethylacetate) and absorbs maximum at 380 nm. The molar absorptivity (ε) and Sandell’s sensitivity of the system being 2.4×103 L·mol−1 cm−1 and 0.027 μg cm−2, respectively. By using the single chromophoric agent (2,3-dihydroxynaphthalene), both uranium and free acidity can be easily and reliably determined separately in the process solution. The relative standard deviations (RSD) are in the range, 0.5–2.0% and 1.5–2.0%, respectively for uranium and free nitric acid determinations. The method has been applied to nuclear fuel process solutions, and the results obtained have been found to be favorably comparable with those obtained from standard methods.
Acknowledgement
Authors are grateful to Director, Additional Directors, Regional Director/ER and Head Chemistry Group, AMD, for giving constant encouragement and inspiration as well as for providing facilities to carry out the research work. The authors are thankful to Director, AMD for giving permission to publish the work.
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©2019 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Cross-section measurements and production of 72Se with medium to high energy protons using arsenic containing targets
- Thorium oxide dissolution in HNO3-HF mixture: kinetics and mechanism
- Highly efficient carbonaceous nanofiber/layered double hydroxide nanocomposites for removal of U(VI) from aqueous solutions
- Effect of solution acidity on the structure of amino acid-bearing uranyl compounds
- A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry
- Experimental investigation of photon attenuation parameters for different binary alloys
- Radiation protective characteristics of some selected tungstates
- New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding
Artikel in diesem Heft
- Frontmatter
- Cross-section measurements and production of 72Se with medium to high energy protons using arsenic containing targets
- Thorium oxide dissolution in HNO3-HF mixture: kinetics and mechanism
- Highly efficient carbonaceous nanofiber/layered double hydroxide nanocomposites for removal of U(VI) from aqueous solutions
- Effect of solution acidity on the structure of amino acid-bearing uranyl compounds
- A novel method for the determination of uranium and free acidity in nuclear fuel process samples by extraction spectrophotometry
- Experimental investigation of photon attenuation parameters for different binary alloys
- Radiation protective characteristics of some selected tungstates
- New high temperature resistant heavy concretes for fast neutron and gamma radiation shielding
