Analysis Methods and Performance of an Automated System for Measuring Both Concentration and Enrichment of Uranium in Solutions PDF Download
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Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
For the 1992 INNM Meeting, we reported on an automated system under development for measuring both concentration and enrichment of uranium in solutions. In this paper, we report on measurement methods, ysis algorithms, and performance of the delivered system. The uranium concentration is measured by a transmission-corrected x-ray fluorescence method. Cobalt-57 is the fluorescing source and a combined 153Gd and 57Co source is used for the transmission measurements. Corrections are made for both the absorption of the exciting 57Co gamma rays and the excited uranium x-rays. The 235U concentration is measured by a transmission-corrected method, which employs the 185.7-keV gamma ray of 235U and a transmission source of 75Se to make corrections for the self-absorption of the 235U gamma rays in the solution samples. Both measurements employ high-resolution gamma-ray spectrometry and use the same 50-ml sample contained in a custom-molded, flat-bottomed, polypropylene bottle. Both measurements are intended for uranium solutions with concentrations ≥0.1 g U/l although at higher enrichments the passive measurement will be even more sensitive.
Author: Publisher: ISBN: Category : Languages : en Pages : 9
Book Description
For the 1992 INNM Meeting, we reported on an automated system under development for measuring both concentration and enrichment of uranium in solutions. In this paper, we report on measurement methods, ysis algorithms, and performance of the delivered system. The uranium concentration is measured by a transmission-corrected x-ray fluorescence method. Cobalt-57 is the fluorescing source and a combined 153Gd and 57Co source is used for the transmission measurements. Corrections are made for both the absorption of the exciting 57Co gamma rays and the excited uranium x-rays. The 235U concentration is measured by a transmission-corrected method, which employs the 185.7-keV gamma ray of 235U and a transmission source of 75Se to make corrections for the self-absorption of the 235U gamma rays in the solution samples. Both measurements employ high-resolution gamma-ray spectrometry and use the same 50-ml sample contained in a custom-molded, flat-bottomed, polypropylene bottle. Both measurements are intended for uranium solutions with concentrations ≥0.1 g U/l although at higher enrichments the passive measurement will be even more sensitive.
Author: Publisher: ISBN: Category : Power resources Languages : en Pages : 724
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
This manual describes the design, operation, and procedures for measurement control for the automated uranium concentration monitor on the 2300 solvent extraction system at the Oak Ridge Y-12 Plant. The nonintrusive monitor provides a near-real time readout of uranium concentration at two locations simultaneously in the solvent extraction system for process monitoring and control. Detectors installed at the top of the extraction column and at the bottom of the backwash column acquire spectra of gamma rays from the solvent extraction solutions in the columns. Pulse-height analysis of these spectra gives the concentration of uranium in the organic product of the extraction column and in the aqueous product of the solvent extraction system. The visual readouts of concentrations for process monitoring are updated every 2 min for both detection systems. Simultaneously, the concentration results are shipped to a remote computer that has been installed by Y-12 to demonstrate automatic control of the solvent extraction system based on input of near-real time process operation information. 8 refs., 13 figs., 4 tabs.
Author: Publisher: ISBN: Category : Languages : en Pages : 5
Book Description
At the Savannah River Site (SRS), accountability measurement of enriched uranium dissolved in H-Canyon is performed using isotope dilution mass spectrometry (IDMS). In the IDMS analytical method, a known quantity of uranium233 is added to the sample solution containing enriched uranium and fission products. The resulting uranium mixture must first be purified using a separation technique in the shielded analytical(''hot'') cells to lower radioactivity levels by removing fission products. Following this purification, the sample is analyzed by mass spectrometry to determine the total uranium content and isotopic abundance. The magnitude of the response of each uranium isotope in the sample solution and the response of the U233 spike is measured. By ratioing these responses, relative to the known quantity of the U233 spike, the uranium content can be determined. A hexane solvent extraction technique, used for years at SRS to remove fission products prior to the mass spectrometry analysis of uranium, has several problems. The hexone method is tedious, requires additional sample clean-up after the purified sample is removed from the shielded cells and requires the use of Resource Conservation and Recovery Act (RCRA)-listed hazardous materials (hexone and chromium compounds). A new high speed separation method that enables a rapid removal of fission products in a shielded cells environment has been developed by the SRS Central Laboratory to replace the hexone method. The new high speed column extraction chromatography technique employs applied vacuum and columns containing tri (2-ethyl-hexyl) phosphate (TEHP) solvent coated on a small particle inert support (SM-7 Bio Beads). The new separation is rapid, user friendly, eliminates the use of the RCA-listed hazardous chemicals and reduces the amount of solid waste generated by the separation method. 2 tabs. 4 figs.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201189103 Category : Environmental sampling Languages : en Pages : 146
Book Description
The 1990s saw significant developments in the global non-proliferation landscape, resulting in a new period of safeguards development. The current publication, which is the second revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the safeguards techniques and equipment used for nuclear material accountancy, containment and surveillance measures, environmental sampling, and data security. New features include a section on new and novel technologies. As new verification measures continue to be developed, the material in this book will be reviewed periodically and updated versions issued.
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Author: P. F. Haughton
Author: Myron O. Fulda
Author: International Atomic Energy Agency
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Author: V. L. Warren
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Author: Charles Anton Prohaska
Author: International Atomic Energy Agency